ML17279A172
| ML17279A172 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 03/27/1987 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17279A171 | List: |
| References | |
| TAC-62045, NUDOCS 8704030589 | |
| Download: ML17279A172 (4) | |
Text
,~Pg AEVI c,~'r, UNITI".rSTAl ES NUCLEAR RF."'~:.,~,'OR.'OMMISSION WASHII'-'<<1'OA, D. C. 20555 0 $
~
Y
'AFETY EVALUATION BY THE OFFI'CE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 38 TO FACILITY OPERATING LICENSE NO. NPF-21 WASHINGTON PUBLIC POMER SUPPLY SYSTEM MPPSS NUCLEAR PROJECT NO.
2 DOCKET NO. 50-397
1.0 INTRODUCTION
By letter from G.
C. Sorensen to E.
G. Adensam dated July 10, 1986, the Washington Public Power Supply System submitted a proposed chanoe to Specification 3.4.2 of the Nuclear Proiect No.
2 (MNP-2) Technical Speci-fications.
The proposed changes are to revise the setpoints for 2 safety/relic'f valves (SRVs) and to revise the setpoint tolerances for all 18 SRVs in the It'NP-2 Technical Specifications.
The licensee also proposed changes to Bases Section 3/4.4.2, the applicable bases section.
2.0 EVALUATION MNP-2 uses 18 Crosby safety relief valves for overpressure protection.
The Crosby safety relief valves have a setpoint opening scatter band range of 4 percent which was measured during qualification testing of the valves.
The present setpoint tolerance in the Technical Specification is +
1 per-cent.
The licensee is requesting that Technical Specification 3.4.2 be revised to use the scatter band of the qualification test for the setpoint tolerances of +1 percent and -3 percent.
The licensee is also proposing that the setpoints for two safety relief valves be changed from 1148 psig to 1150 psig to be consistent with the General Electric design documents.
Presently, the setpoints for the 18 safety relief valves are as follows: 4 at 1205 psig,'
at 1195 psig, 4 at 1185 psig, 4 at 1175 psig, and 2 at 1148 psig.
The overpressure protection evaluation considers only the maximum or upper value of the opening pressures of the safety relief valves, which will be maintained by the proposed upper tolerance limit of 1 percent.
The plant operating pressure is 1020 psig.
The lower tolerance limit of -3 percent would actuate a safety relief valve for the minimum setting at about 1115 psig during plant operation.
This lower tolerance provides adequate simIer margin which will reduce the potential for spurious openings.
This simmer margin is the difference between the lowest safety relief valve set pressure and the reactor pressure vessel operating pressure.
Based on our review of the information provided by the licensee, the staff concludes that the proposed changes do not affect the overpressure protec-tion analyses or plant performance, and therefore, are acceptable, 04030889 8703>
- PDR,
'ADOCK 05000397 PDR
- 3. 0 ENVIRONHENTAL CONSIDERATION This amendment involves a change in the use of a facility component located within the restricted area as defined in 10 CFR Part 20.
The staff has determined that this amendment involves no significant increase in the
- amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure.
The Commission has previously issued a proposed finding that this amendment involves no significant hazards consideration, and there has been no public comment on such finding.
Accordingly, this amerdment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b),
no environmental impact statement or environ-mental assessment need be prepared in connection with the issuance of this amendment.
4.0 CONCLUSION
The Commission made a proposed determination that the amendment involves no.significant hazards consideration which was published in the Federal Register (51 FR 32282) on September 10, 1986, and consulted with the state of Washington.
No public comments were received, and the state of Washington did not have any comments.
We have concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health ard safety of the public will not be endangered by operation in the proposed
- manner, and (2) such activities will be conducted in compliance with the Commission's regula-tions and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
Y. Li, NRR Dated:
Harch 27, 1987
AMENDMENT NO.
38 TO FACILITY OPERATING LICENSE NO. NPF-21 WPPGS NUCLEAR PROJECT NO.
2 DISTRIBUTION:
CDocket-No
. 50-397 NRC PDR Local PDR PRC System NSIC BWD-3 r/f JBradfute (2)
EHyl ton (1)
EAdensam
- Attorney, OELD CMiles RDiaas JPartlow EJordan BGrimes LHarmon TBarnhart (4)
EButcher
II'