ML20236B037
| ML20236B037 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/15/1987 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20236B026 | List: |
| References | |
| NUDOCS 8710230303 | |
| Download: ML20236B037 (2) | |
Text
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SAFETY EVALUATION BY THE OFFICE 0F NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT N0.133 T0 FACILITY OPERATING LICENSE NO. DPR-50 METROPOLITAN EDIS0N COMPANY-
' JERSEY. CENTRAL POWER AND LIGHT COMPANY-PENNSYLVANIA ELECTRIC COMPANY GPU NUCLEAR CORPORATIO_N, c
THREE MILE ISLAND NUCLEAR STATION,' UNIT NO. 11 II DOCKET NO.~50-289 i
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1.0 INTRODUCTION
I The current Three Mile Island, Unit'1 (TMI-1) Technical Specifications (TS)
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_ require that two (2) Main Steam Safety Valves.(MSSVs):per steam generator shall be operable when the Reactor Coolant System Temperature is between 250*F and hot shutdown conditions. When the reactor :is above-hot shutdown-condition, all eighteen (18).MSSVs shall.be operable.
In a letter dated February 5 -1987, GPU Nuclear Corporation (licensee) stated If that the current TS do not provide for efficient in-place. testing of MSSVs '
l[l following valve maintenance during cold shutdown or refueling. The proposed l
modifications of the TS would allow for a nominal. increase in power of. no more than 5% while the MSSVs and.other functional testing are being performed.
I 2.0 EVALUATION l5 The licensee proposed TS Section 3.4.1.2.2 states that with the reactor from HOT SHUTDOWN to 5% power and having been subcritical for'at least I hour, two Main Steam Safety Valves per Steam Generator shall be.0PERABLE provided the over power trip setpoint in the RPS is set to less than 5% full power. With j
less than two Main. Steam Safety Valves per Steam Generator OPERABLE, restore 1
at least two-Main Steam Safety Valves to OPERABLE status for each Steam Generator within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or be in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
The licensee provided the results of a calculation which demonstrated that two MSSVs on either once through steam generator are more than sufficient tt release the amount of steam produced from the reactor decay heat, reactor coolant pump heat.and sensible heat from feedwater. The staff has evaluated the assumptions used in the licensee's calculation and find.that they are conservative.
According to the proposed TS Section 3.1.1.2a, both steam generators are' required to be operable when the reactor coolant average temperature is above 250*F. This TS assures that a total of four MSSVs are available when the reactor is operated up to 5% power. Under these conditions, the total available steam relief capacity is more than'two times the calculated minimum requirement.
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Based on the above evaluation, the staff concludes that the licensee. proposed -
changes'of TS Section 3.4.1.2.2 and its bases on pages 3-26b will ensure i
sufficient MSSV' relieving capacity when the TMI-1 is operated up to 5%
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. power. The proposed TS meet the applicable regulatory guidance and requirements and therefore, are acceptable.
3.0 ENVIRONMENTAL CONSIDERATION
This amendment changes a requirement with respect to installation or use of a facility component located within the restricted' area as defined in 10 CFR Part 20.-
We have determined that the amendment involves.no signi-
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ficant increase in the amounts, and no significant change-in the types, of. any effluents that may be released offsite, and that. there is no i
significant increase in individual or cumulative occupational radiation exposure. The Comission has previously issued a proposed finding that this amendment involves no significant hazards consideration and there i
t has been no public comment on such finding. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set-forth in 10 CFR 51.22/c)(91. Pursuant to 10 CFR 51.72(b), no environmental impact l4 statement or environmental assessment need be prepared in connection with the issuance of this amendment.
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4.0 CONCLUSION
We have concluded, based on the considerations discussed above, that: (1) l ['
there is reasonable assurance that the health and safety.of the public will not be endangered by operation in the proposed manner, and (2) such j
activities ~ will be conducted in compliance with the Comission's regulations t
and the issuance of this amendment will' not be inimical to the comon defense and security or to'the health and safety of the public.
-1 Dated: October 15, 1987 j.
h Principal Contributor:
F C. Liang i
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