.. -. I •-

Distribution: DOcket File 50·320

· NRC POR LPOR

TCPoindexter RBosnak Service List

DocJcet Ho. 50-320 • TERA TMIPO R/F THI Site R/F BJSnyder LBarrett

(attached)

Mr. Gale K. Hovey V1ce President and

01 rector of TMI -2 Metropolitan Edison Collpany P.o. Box 480 Middletown, Pennsylvania 17057

DHr Mr. Hovey:

AFasano (TMI Site) RConte (TMI Site) MOuncan LChandler, OELD OBrinkman I&E (3) ACRS (16) OLynch RWeller

The NRC staff has reviewed your request of Apr11 18, 1980 (Met. Ed. letter Tll 176 f1"0111 R. C. Amold to Harold Denton) for relief fi'OII the Inservice Inspection Prograa requ11"MMnts of 10 CFR Part 50.551. Your application proposed that in lieu of c:a~Plyfng with the requi.--nts of 10 CFR Part SO.SSa, testing/surveillance be perfo,.d in accordAnce with the Recovery Technical Specifications/Recovery Operations Plan issued with the Feb,..ry 11, 1980 Order. You detanrinld that the provisions of IWA-2400 of Sect1on XI of the ASHE Boiler and Pressure Vessel Code, 1974 Ed1tion, Sunmer 1975 Addenda which provide for utand1ng the inspection interval for a penod of t1• equiv­alent to the length of the shutdown are appHcable to TMI-2. We agree that the inspection interval should be extended for a period equivalent to the shutdown period.

You also detena1ned that testing of pwaps during shutdown penods ts not required as pet' IWP-3400 of the Code and stated that you intend to discontinue testin9 pwaps which aN no longer considered safety related. In general, we find the discontinuance of pwap testing for thOse system no longer considered safety related acceptable. All pUIIps tn thOse systaa required to mitigate the conse­quences of an accident and •inta1n the reactor in 1ts present safe shutdown condition are included in and required operable by the Recovery Technical Speci­ffcatfons. These J)Uq)S should be tested at least once per 31 days. These tests should include u a .-ini- running for fifteen 111nutas and JDHSurement of at least one of the following : discharge pressure flow-rata or differential pressure. Spec1ftc relief requests for tndhtdull pullpS are. required to be subll1ttad 1f the above crt ter1a canr.Jt be •t.

Your request for relief defined Cltegory A valves (per IWV-2110 of the Code) IS being exclusively containaent isolation valves and stated that these valves will not be full stroked exercised in order to utntain contail'8nt tsolatfon but will be 1111intained according to the Recovery Technical Specifications. We agree that those containment isolation valves which are closed should ~in closed and not be exercised. However, if a contlhaent isolation valve ts opened and then closed after a period of tiaae, 10 CFR Part 50, Appendfx J. Type •c• testing wfll be re· qu1red to verify fts containment isolation function .

Biososo 1-L.'\

·-, .II""'

Mr. Galt K. Hovey

You also. stated that CAtegory 8 and C valves i n systta out of service wi ll not bt tast8d u per the Code but will be tested according to the Rllcovery Technical Spec:tftcattons. We recognize that CAtf901"1 8 and c val ves tn systee out of service need not bt tnt8d during the shutdown period. However, we believe thlt all CAtegory 8 and C valves in safe~ relat.d syst.s tn santee should be uerc1sed at least oace per 92 ~ arw practical to cletanl1ne their operational rudtness. Relief f,. the tat requ1,.._ts for Cltegory 8 and C valva tn safe~ rwlat8d sysU. spectfttd above w111 have to bt sue.tttad on an tndhtdual valve bu1s.

Based on .. ttng the above r.qut..-sts, • f1nd that granting tM specific Nlttf stat8d herein 1s author1ztd by law and will not endanger 11ft or prope~ or the ccc 1 ,., defense and securi fiY and 1s otherw1 se t n the pub 11 c tntarat, and, thtrwfon~, grant the r~q.sttd rwltef. tta.ev.r, you should note that thts reltef docts not apply to the Mint Otay Heat ~val Syst. stnce ... lttf for tt 1s bttng constdlrwd tn a separate action.

A copy of the Notice of Issuance 1s enclosed.

fnclosure : Noti ce of Issuance

Stneerwly,

·)j Bernard J . Snyder, Prog,... Director TMI Progr18 Off1 ce Off ice of Nuclear Reactor Regulation

OFFICIAL RECORD COPY

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POOR ORIGINAL

UNITED STATES NUCLEAR REGULATORY COMMISSION

DOCKET NO. 50-320

METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER AND LIGHT COMPANY

PENNSYLVANIA ELECTRIC COMPANY

GRANTING OF RELIEF FROM ASME SECTION XI

INSERVICE INSPECTION (TESTING) REQUIR~~ENTS

7590-01

The U.S. Nuclear Regulatory Commission (the Commission) has granted relief

from certain requirements of the ASME Code, Section XI, "Rules for Inservice

Inspection of Nuclear Power Plant Components" to Metropolitan Edison Company,

Jersey Central Power and Light Company, and Pennsylvania Electric Company in

accordance with the provisions of 10 CFR ~SO.SSa. The relief relat~s to the

revised inservice testing program for pumps and valves for Three Mile Island

Nuclear Station, Unit 2, located in Dauphin County, Pennsylvania. The ASME Code

~quirements are incorporated by reference into the Commission's rules and regu­

lations i n 10 CFR Part 50. The relief is effective as of its date of issuance.

The relief consists of exemption from the requirements for measuring certain

parameters in the Pump Testing Program and revised schedules for conducting valve

stroking tests in the Valve Testing Program. Relief was also granted from the

reauirement for inservice inspection of Class I, II, and III comoonents for a

period equivalent to the length of the TMI 2 shutdown.

The request for relief complies with the standards and requirements of the

Atomic Energy Act of 1954, as amended (the Act), and the Commiss ion's rules and

regulations. The Commission has made appropriate findings as ~equired by the ~ct

and the Commission's rules and regulation in 10 CFR Chapter I, wnich are set forth

81 05050 ~3()

.. 7590-01

-2-

in the letter granting relief. Prior public notice of this action was not

required since the granting of this relief from ASME Code requirements does

not involve a significant hazards consideration.

The Commission has determined that the granting of this relief will not

result in any si gnificant environmental impact and that pursuant to 10 CFR

§51 ,5(d)(4) an environmental impact statement or negative declaration and

environmental impact appraisal need not be prepared in connection with this

action.

For further details with respect to this action, see (1) the request

for relief (2) dated April 18, 1980, and (2) the Commission's letter to the

licensee dated April 27, 1981.

These items are available for public inspection at the Commission's Public

Document Room, 1717 H Street, N.W., Washington, D.C. 20555 and at the Government

Publications Section, State Library of Pennsylvania, Education Building, Commonwealth

and Walnut Streets, Harrisburg, Pennsylvania 17126. A copy of item (2) may be

obtained upon requ~st addressed to the U.S . Nuclear Regulatory Commission,

Washington, D.C. 20555 , Attention : Director, TMI Program Office.

Dated at Bethesda, Mar;land this 27th day of April, 1981.

FOR THE NUCLEAR REGULA~ORY COMMISSION

~~~ -~7,~~ Bernard J. Snyde~Program Director Three ~ile Island Program Office Office of ~uclear Reactor Regulation