ACCELERATED DIS UTION DEMONSTPATION SYSTEM

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9402150138 DOC.DATE: 94/02/04 NOTARIZED: YESFACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina

AUTH.NAME AUTHOR AFFILIATIONROBINSON,W.R. Carolina Power 6 Light Co.

RECIP.NAME RECIPIENT AFFILIATIONDocument Control Branch (Document Control Desk)

DOCKET05000400

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SUBJECT: Application for amend to license NPF-63,revising"Containment Sys — Vacuum Relief Sys" to requireModes 1-4 w/one vacuum relief sys inoperable,systo operable status within 72 h,per NUREG-1431.

DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCLTITLE: OR Submittal: General DistributionNOTES:Application for permit renewal filed.

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Carolina Power & Light CompanyPO Box 165New Hill NC 27562

William R. RobinsonVice PresidentHarris Nuclear Plant

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Letter Number: HO-940239

SERIAL: HNP-94-00610 CFR 50.90

United States Nuclear Regulatory CommissionATTENTION: Document Control DeskWashington, DC 20555

SHEARON HARRIS NUCLEAR POWER PLANTDOCKET NO. 50-400/LICENSE NO. NPF-63REQUEST FOR LICENSE AMENDMENTCONTAINMENTVACUUMRELIEF SYSTEM

Gentlemen:

In accordance with the Code of Federal Regulations, Title 10, Parts 50.90 and 2.101,Carolina Power & Light Company (CP&L) hereby requests a revision to the TechnicalSpecifications (TS) for the Shearon Harris Nuclear Power Plant (SHNPP).

The proposed amendment revises the Action Statement associated with TechnicalSpecification 3.6.5, Containment Systems - Vacuum Relief System. Currently, theSpecification requires an inoperable containment vacuum relief system (CVRS) to berestored to an operable status within four hours. Consistent with NUREG-1431 (the newStandard Technical Specifications), the proposed amendment requires that the inoperableCVRS be restored to an operable status within seventy-two hours. The proposed time periodis consistent with other Limiting Conditions For Operation for the loss of one train of asystem that is required to mitigate the consequences of a loss of coolant accident or otherdesign basis accident.

Enclosure 1 provides a detailed description of the proposed changes and the basis for thechanges.O

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Enclosure 2 details, in accordance with 10 CFR 50.91(a), the basis for the Company'sdetermination that the proposed changes do not involve a significant hazards consideration.

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Enclosure 3 provides an environmental evaluation which demonstrates that the proposedamendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental assessment needsto be prepared in connection with the issuance of the amendment.

".'ii000:P State Road113d NewHill NC Tel 919362-2502 Fax 919362-6950

,Document Control DesHNP-94-006 / Page 2

Enclosure 4 provides page change instructions for incorporating the proposed revision.

Enclosure 5 provides the proposed Technical Specification pages.

In accordance with 10 CFR 50.91(b), CP&L is providing the State of North Carolina witha copy of the proposed license amendment.

In order to allow time for procedure revision and orderly incorporation into copies of theTechnical Specifications, CP&L requests that the proposed amendment, once approved bythe NRC, be issued such that implementation willoccur within sixty days of issuance of theamendment.

Please refer any questions regarding this submittal to Mr. D. C. McCarthy at (919) 362-2100.

Yours very truly,

W. R. Robinson

MGW

Enclosures:1. Basis for Change Request2. 10 CFR 50.92 Evaluation3. Environmental Considerations4. Page Change Instructions5. Technical Specification Pages

W. R. Robinson, having been first duly sworn, did depose and say that the informationcontained herein is true and correct to the best of his information, knowledge and belief;and the sources of his information are officers, employees, contractors, and agents ofCarolina Power & Light Company.

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CC: Mr. Dayne H. BrownMr. S. D. EbneterMr. N. B. LeMr. J. E. Tedrow

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ENCLOSURE SERIAL: HNP-94-006

ENCLOSURE 1

SHEARON HARRIS NUCLEAR POWER PLANTNRC DOCKET NO. 50-400/LICENSE NO. NPF-63

REQUEST FOR LICENSE AMENDMENTCONTAINMENT VACUUM RELIEF SYSTEM

BASIS FOR CHANGE RE UEST

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The Containment Vacuum Relief System (CVRS) is designed to assure the structuralintegrity of the Reactor Containment Building in the event of an inadvertentactuation of the containment spray system. The CVRS consists of two independentvacuum relief lines, each sized to protect the containment structure againstexcessive negative pressure differential. Technical Specification 3.6.5,Containment Systems - Vacuum Relief System, specifies in the Action Statementthat in Modes 1-4 with one vacuum relief system inoperable, the system berestored to OPERABLE status within four hours or be in at least HOT STANDBYwithin the next six hours. This is based on the guidance provided in NUREG-0452,Standard Technical Specifications For Westinghouse Pressurized Water Reactors,Draft Revision 5 from which the Shearon Harris Nuclear Power Plant TechnicalSpecifications were modeled.

Pro osed Chan e

The proposed amendment revises the Action Statement associated with TechnicalSpecification 3.6.5 to require that in Modes 1-4 with one vacuum relief systeminoperable, the system be restored to OPERABLE status within seventy-two hoursor be in at least HOT STANDBY within the next six hours.

Basis

Changing the Action Statement from four hours to seventy-two hours is consistentwith the guidance contained in NUREG-1431, Standard Technical Specifications,Westinghouse Plants, Bases, Volume 3 (LCO 3.6.12, Vacuum Relief Valves). The CVRSis not an ESF system nor does it provide protection features for any accidentanalyzed in Chapter 15 of the FSAR. The revised Standard Technical Specificationsallow for a seventy-two hour restoration period for an inoperable train oftwo-trained ESF systems. This amendment proposes to apply this level of controlon this non-ESF equipment.

Conclusions

The application of the seventy-two hour completion time to the CVRS isconservative, since the time period is consistent with that specified fortwo-trained ESF systems which mitigate FSAR Chapter 15 accidents. The ShearonHarris Nuclear Power Plant CVRS is designed to assure the structural integrityof the containment building in the event of an inadvertent actuation of thecontainment spray system which is not an FSAR Chapter 15 accident. Therefore, theproposed seventy-two hour completion time for the CVRS is conservative on thiscomparative basis.

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ENCLOSURE SERIAL: HNP-94-006

ENCLOSURE 2

SHEARON HARRIS NUCLEAR POWER PLANTNRC DOCKET NO. 50-400/LICENSE NO.. NPF-63

REQUEST FOR LICENSE AMENDMENT

CONTAINMENT VACUUM RELIEF SYSTEM

10 CFR 50.92 EVALUATION

The Commission has provided standards in 10 CFR 50.92(c) for determining whethera significant hazards consideration exists. A proposed amendment to an operatinglicense for a facility involves no significant hazards consideration ifoperationof the facility in accordance with the proposed amendment would not: (1) involvea significant increase in the probability or consequences of an accidentpreviously evaluated, (2) create the possibility of a- new or different kind ofaccident from any accident previously evaluated, or (3) involve a significantreduction in a margin of safety. Carolina Power & Light Company has reviewedthis proposed license amendment request and determined that its adoption wouldnot involve a significant hazards determination. The bases for thisdetermination are as follows:

Pro osed Chan e

The proposed amendment revises the Action Statement associated with TechnicalSpecification 3.6.5, Containment Systems - Vacuum Relief System. Currently, theSpecification requires an inoperable containment vacuum relief system (CVRS) tobe restored to an operable status within four hours or be in at least HOT STANDBY(Mode 3) within the next six hours. The proposed amendment requires that theinoperable CVRS be restored to an operable status within seventy-two hours or bein at least HOT STANDBY within the next six hours. The proposed time period isconsistent with other Limiting Conditions For Operation for the loss of one trainof a .system that is required to mitigate the consequences of a loss of coolantaccident or other design basis accident; although the CVRS is not required tomitigate a loss of coolant or other design basis accident.

Basis

This change does not involve a significant hazards consideration for thefollowing reasons:

The proposed amendment does not involve a significant increase in theprobability or consequences of an accident previously evaluated.

The proposed amendment does not physically alter the plant in any manner.The proposed amendment does not introduce any new equipment nor does itrequire any existing equipment or systems to perform a different type offunction than they are currently designed to perform. The proposedamendment to Technical Specification 3.6.5 allows additional time torestore an inoperable containment vacuum relief system to operable status.Changing the completion time to seventy-two hours remains quiteconservative for this non-ESF syst: em since a seventy-two hour restorationtime is specified for two-train ESF systems which mitigate Final SafetyAnalysis Report (FSAR) Chapter 15 accidents. The CVRS is designed toprotect the structural integrity of containment during an inadvertentactuation of the containment spray system, which is not an FSAR Chapter 15

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accident. Therefore, there would be no increase in the probability orconsequences of an accident previously evaluated.

The proposed amendment does not create the possibility of a new ordifferent kind of accident from any accident previously evaluated.

The proposed amendment does not introduce any new equipment nor does itrequire any existing equipment or systems to perform a different type offunction than they are currently designed to perform. Therefore, theproposed changes do not create the possibility of a new or differentkind of accident from any accident previously evaluated.

The proposed amendment does not involve a significant reduction in themargin of safety.

The proposed amendment to Technical Specification 3.6.5 allows additionaltime to restore an inoperable containment vacuum relief system to operablestatus. Changing the completion time to seventy-two hours remainsconservative since a seventy-two hour restoration time is specified fortwo-train ESF systems which mitigate FSAR Chapter 15 accidents. The CVRS

is designed to protect the structural integrity of containment during aninadvertent actuation of the containment spray system, which is not anFSAR Chapter 15 accident. Therefore, the proposed changes do not involvea significant reduction in a margin of safety as defined in the TechnicalSpecifications or FSAR.

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ENCLOSURE SERIAL: HNP-94-006

ENCLOSURE 3

SHEARON HARRIS NUCLEAR POWER PLANTNRC DOCKET NO. 50-400/LICENSE NO. NPF-63

REQUEST FOR LICENSE AMENDMENTCONTAINMENT VACUUM RELIEF SYSTEM

ENVIRONMENTAL CONSIDERATIONS

10 CFR 51.22(c)(9) provides criterion for and identification of licensing andregulatory actions eligible for categorical exclusion from performing anenvironmental assessment. A proposed amendment to an operating license for afacility requires no environmental assessment if operation of the facility inaccordance with the proposed amendment would not: (1) involve a significanthazards consideration; (2) result in a significant change in the types orsignificant increase in the amounts of any effluents that may be releasedoffsite; (3) result in an increase in individual or cumulative occupationalradiation exposure. Carolina Power 6 Light Company has reviewed this request anddetermined that the proposed amendment meets the eligibility criteria forcategorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to10 CFR 51.22(b), no environmental impact statement or environmental assessmentneeds to be prepared in connection with the issuance of the amendment. The basisfor this determination follows:

Pro osed Chan e

The proposed amendment revises the Action Statement associated with TechnicalSpecification 3.6.5, Containment Systems - Vacuum Relief System. Currently, theSpecification requires an inoperable containment vacuum relief system (CVRS) tobe restored to an operable status within four hours or be in at least HOT STANDBY(Mode 3) within the next six hours. The proposed amendment requires that theinoperable CVRS be restored to an operable status within seventy-two hours or bein at least HOT STANDBY within the next six hours. The proposed time period isconsistent with other Limiting Conditions For Operation for the loss of one trainof a system that is required to mitigate the consequences of a loss of coolantaccident or other design basis accident; although the CVRS is not required tomitigate a loss of coolant accident or other design basis accident.

Basis

The change meets the eligibilitycriteria for categorical exclusion set forth in10 CFR 51.22(c)(9) for the following reasons:

As demonstrated in Enclosure 2, the proposed amendment does not involve asignificant hazards consideration.

The proposed amendment does not result in a significant change in thetypes or significant increase in the amounts of any effluen'ts that may bereleased offsite.

The proposed amendment allows additional time to restore an inoperablecontainment vacuum relief system to operable status. The proposedamendment does not introduce any new equipment nor does it require anyexisting equipment or systems to perform a different type of function than

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they are currently designed to perform. As such, the change can not affectthe types or amounts of any effluents that may be released offsite.

The proposed amendment does not result in an increase in individual orcumulative occupational radiation exposure.

The proposed amendment allows additional time to restore ancontainment vacuum relief system to operable status. Nosurveillances or testing result from the proposed amendment.the amendment has no affect on either "individual oroccupational radiation exposure..

inoperableadditionalTherefore,cumulative

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ENCLOSURE SERIAL: HNP-94-006

ENCLOSURE 4SHEARON HARRIS NUCLEAR POWER PLANT

NRC DOCKET NO. 50-400/LICENSE NO. NPF-63REQUEST FOR LICENSE AMENDMENT

CONTAINMENT VACUUM RELIEF SYSTEM

PAGE CHANGE INSTRUCTIONS

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