ML20207S540

Safety Evaluation Supporting Amend 125 to License DPR-50

ML20207S540
Person / Time
Site:	Crane
Issue date:	03/09/1987
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20207S531	List: ML20207S530 ML20207S540
References
NUDOCS 8703200006
Download: ML20207S540 (2)

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j NUCLEnR REGULATORY COMMISSION WASHINGTON, D. C. 20555

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UFETY EVAlUALION BY THF OrriCE OF Nt'CLEAP PEACTCF PEGUI AT!ON SUPP0CTIf4 AMENDMENT P 0.125 TO FACIL ITY OPERATit'G LICENSE NO. DPP-50 ~

t'FTROP0t ITAN EDISON COMphNY OfRSEY'TUTI AL POWER AND LIGHT'TTIMPAMY PENFSYLVANIA ELECTF.!C COMPANY g

GP NUCLEAR CORPORATION THPEF MILE ISLAND NUCLEAR STATION, UNIT NO. !

00CVET NO. 50-789 i If,TRODUCTICN i

Py letter date~d November 3,19E6; cs supplemented November 19, 1986 GPU Nuclear Corporation (GPU or the licensee) reouested an amendment of the Technical Specifications (TSs) appended to Facility Operatino License No.

DPR-f0 for the'Three Mile Island Nuclear Station, Unit No. 1 (TMI-1).

The proposed amendment would revise TS 3.4.1.2 to permit plant operation with only two Main Stear Safety Valves (MSSVs) per steam generator operat'le when the Peactor Coolant System 1RCS) temperature is between 250 F and that correspondino-to hot shutdown conditions (i.e., FCS is creater than 5?5"F and reactor subcritical). Additionally, the reactor must h' ave been suberitical for at least one hour befpre the.ner MSSV operatsility r equirements would apply.

This chance will allow for higher F,lant pressure and temperature conditions in-order to conduct FSSV testina while the reactor is subdritical. When the reactor is above hot shutdown conditions, or has been subcritical for less than one hour, the current TS operability reouirements apply.

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The MSSVs provide secondary system overpressure protection durino all modes of plant operation,.

Currently, TS 3.4.1.2 requires all 18 MSSVs to be

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operable for plant operation with RCS temperature above 250*F.

If any of.the MSSVs are not operable, the maximum overocwer trip setpoint is lowered per the requirements of.the T5 3.4.1.?.

The licensee has asserted that. the current TS does not provide conditions for MSSV testing after valve maintenance durfno the cold shutdown or refuel'inq modes since mein stem.-

pressure of approximately 900 psio (saturation temperature 53CF) is necaed for testino of the MSSVs.

EVALUATION i

The licensee, in a letter dated November 19, 1986, provided iihe results of an analysis which demonstrates that one MSSV is sufficient to relieve the amount of heat added by the reactor coolant pumps and the decay heat generated from t

the core one hour followina a reactor trip. The licensae's analysis assumas:

(1) steam conditions are dry saturated, (?) atmospheric dLmp valves remain l

closed, (3) the reactor has been subcriticel for at least one hour, and l

(4) a decay heat value of 1.2 times the ANS standard (ANS 5.1, 1979),

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7-Based on th5l data for.the hSSV relieving capacity as presented by the 5

licensee's sucmittal, WE aeree With the license *'s conclusion that one ~45Y is sufficient for RCS heat rerevtl during hot shutdowr conditions cre bner fellowing a reactor trip, if rce the proposed TS 3.4.1.? requires two operable FSSVs per steam cenerator during plant creration when PCS temperature is between 250*F and that correspondino' to hot. shutdowr conditions, with the reactor subcritical for at letst one hour, we consider that the proposed TS prevides ample narcin for relieving capacitv.

3" Ve' have alsc reviewed the licensee's modified beses for proposed TS 3.t.).?

and fird them acceptable, t '

The propoced chance is supported by the licensee's analysis since adecuate steam relieving capacity will still be maintained durino heatup and hot shutdown cperations. Therefore, we conclude that the proposed change of 15 3.4.1.? is acceptable.

ENVIRCNFENTAL CONSIDERATION This amendmsnt involves a change in the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20.

We have deternined that the amendrent involves no significant increase in the amounts, and ne significant change in the types, of any effluents that may be.

releated offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previousiv 3

issued a proposed finding that this amendment involves no sionificant hazards consideration and there has been no public comment on such finding. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.??(c)(9).

Pursuant to 10 CFR 51.??(b), no envircrmental impact statement or environmental assessment need be prepared in connec+ien with the issuance of this amendment.

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CONCLUSTON We have concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will ret be endanaered by operation in the proposed navner, and [?) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not le inimical to the common defense aric s(curity or to the health and safety of the public.

1. Datfd)

March 9,1987 Principal, Contributor:

C. Lierc

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