ML19210A711

Tech Spec Change Request 82 Supporting Licensee Request to Change DPR-50,App a Re Revision for Limitation of Written Procedures Which Include Operator Action to Be Taken in Event of Small Break LOCA

ML19210A711
Person / Time
Site:	Three Mile Island
Issue date:	06/15/1978
From:	Herbein J METROPOLITAN EDISON CO.
To:
Shared Package
ML19210A710	List: ML19210A709 ML19210A711
References
NUDOCS 7910310529
Download: ML19210A711 (3)

Text

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METROPOLITAN EDISON CCMPANY JERSEY CE'ITRAL PCWER & LIGHT COMPANY AND PENNSYLVANIA ELECTRIC COMPNIY TF2.EE MILE ISLA:ID NUCLEAR STATION L7IIT 1 Operating License No. EPR-50 rocket No. 50-289 Technical Stecification Chance Request No. 82 This Technical Specification Change Request is submitted in support of Licensee's request to change Appendix A to Operating License No. DPR-50 for Three Mile Island Nuclear Station Unit 1. As a part of this request, proposed replacement pages for Appendix A are also included.

METROPOLITri EDISON C05'PANY

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By Vice President Sworn and subscribed to me this b day of , 1978.

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ATP Notaryfupic pp O2032.3 J. ~O2 IIE~t .

f %t try Pt,',l'O, D,c e ,'.r a, Z M.3 CO.

My Ccem.:ss:en Ex;;rc Jan.25,1952 7910310 f2 9 0 1490 306

Three ile Island Nuclear Station Unit 1 (TMI-1)

Operating License No. LPR-50 Docket No. 50-289 Technical Specification Chance Recuest No. 82 j

rgj The licensee requests that the attached page replace page 6-11 of the existing Technical Specifications.

Reaso.'.s for Chance Recuest In our aH 3reak LOCA Sutrittal, GO.L 0778, April 27,1978, Met-Ed ce==itted to su~:ui Technical Specificati:n Changes. This co=mitment was requested by

-b- ' -- ' sion to assure that appropriate operator action is taken in the ev at

. 1,. _v v.a- -.

Safe;" -/C "*'4 ^n Justif: ring Chance This change provides a Te:hnical Specification requirement for i=plementaticn cf written pr:cedures whi:h in:lude the operator actica to be taken in the event of a :-l 3reak LCCA. :-~~ =d"-as are currently in place at TMI-1 which incluie he Operator acti:n to ' e taken in the event of a Fmn11 Break LCCA.

Ee:ause this change is ai ' 'strative in nature, we have determined that:

i} the probability ci :::urrence or the consequences of an accident or talfunction of equipment i pertant to safety, previously evaluated in the safety analysis rep:rt is not increased.

ii) The possibility of an accident er -a' function of a different type than any evaluated previously in the safety analysis report is not created.

iii) The targin of safety defined in the basis for any Technical Specification is not reduced.

License Amendment Classification (10 CFR,170.22)

Because this amendnent was requested by the NRC and is being submitted for the convenience of the NRC, no remittance is required.

1490 307

, ' 6.8 PROCEDURES 6.8.1 Written procedures and administrative policies shall be establisheu, implemented and maintained that meet or exceed the zequirements and recommendations of Sections 5.1 and 5.3 of A'ISI NI8.7-1972 and Ap-pendix "A" of USNRC Regulatory Guide 1.33 November 1972 except as provided in 6.8,2 and 6.8.3 below.

Implementption of the Fire Protection Progran shall be by means of written procedures.

Written procedures, which include the operator action to be taken in the event of a Small Break LOCA shall be implemented.

6.8.2 Each nuclear safety related procedure and administrative policy of 6.8.1 above, and changes thereto, shall be rev4ved by the Plant Operations Review Committee and approved by the Unit Superintendent prior to implementation and periodically as may be set forth in each document.

6.8.3 Tempor'ry changes to procedures of 6.8.1 above may be made provided:

a. The intent of the original procedure is not altered.

b. Tne change is approved by two = embers of the plant management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.

c. The change is documented, reviewed by the Plant Operations Review Committee and approved by the Unit Superintendent within 7 days of imple=entation.

6- 1 1490 308