ML17278A835
| ML17278A835 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 05/13/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17278A834 | List: |
| References | |
| TAC-60548, NUDOCS 8605190359 | |
| Download: ML17278A835 (6) | |
Text
t UNITEDSTATES NUCLEAR REGULATORY COMMISSION e
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO.
24 TO FACILITY OPERATING LICENSE NO. NPF-21 WASHINGTON PUBLIC POWER SUPPLY SYSTEM WPPSS NUCLEAR PROJECT NO.
2 DOCKET NO. 50-397
1.0 INTRODUCTION
2.0 By letter dated January 17, 1986, the Supply System requested a number of revisions to the WNP-2 Technical Specifications, Table 3.6.3-1 (Primary Isolation Valves).
One of the revisions involved the conversion of a locked-closed, manual isolation valve to a normally closed, motor-operated isolation valve.
To permit early implementation of the capability provided by this modification, this safety evaluation addresses only this valve conversion item.
The other proposed revisions requested by the Supply System will be addressed in a separate licensing action.
EVALUATION The proposed revision involves a valve designated by the licensee as FPC-V-149.
At present this valve is listed in section 'c'f Table 3.6.3-1 of the WNP-2 Technical Specifications (page 3/4 6-26) as a Manual Contain-
.ment Isolation Valve and is described as a "Fuel Pool/Suppression Pool Cooling" valve.
Table 6.2-12 of the Final Safety Analysis Report (FSAR) for the facility further describes the valve as a six-inch, manually oper-
- ated, globe valve that is normally locked closed.
Table 6.2-12 (page 6.2-129) also indicates valve FPC-V-149 is one of four Containment Isolation Valves provided for the Suppression Pool Cleanup suction and return lines.
The other three isolation valves are FPC-V-153, 154 and 156.
Table 6.2-12 indicates these three valves ate six-inch, motor-operated gate valves that are normally closed.
The Table also indicates these'alves receive an isolation signal upon occurrence of low water level in the reactor vessel or high pressure in the drywell.
The revision proposed by the licensee would change the operation of the valve and move FPC-V-149 from Section 'c'Manual Isolation Valves) of the Technical Specification Table 3.6.3-1 to Section 'a'Automatic Isolation Valves).
The valve would thus be grouped with the other Fuel Pool/
Suppression Pool valves listed above.
The maximum stroke time for FPC-V-149 stated in Table 3.6.3-1 would be the same as for the other three valves.
This proposed revision is prompted by 'the licensee's plant modification which has resulted in FPC-V-149 being equipped with a motor operator and provided with an automatic isolation signal.
Further the actual modifica-tion involved replacing the six-inch, manual globe valve with a six-inch, 8605190359 860513 PDR ADOCN, 05000397 p
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motor-operated gate valve.
FPC-V-149, therefore, is basically similar to the other automatic isolation valves described above.
The licensee states the modification will (I) allow the Fuel Pool Cooling (FPC) system deminer-alizers also to be used for cleanup of the suppression pool water inventory; and (2) allow the FPC system to be used to maintain water level in the suppression pool.
The licensee adds that "Without the ability to use this automatic valve, suppression pool level will have to be maintained utilizing an RHR pump, thereby unnecessarily challenging an ECCS function."
The acceptability of the proposed revision to the Technical Specifications hinges on the acceptability of the substitution of a motor-operated isolation valve for the present locked-closed manual valve (FPC-V-149).
Based on Criterion 56, which allows either type of valve to provide the required isolation function, we conclude the modification is appropriate
- and, accordingly, the proposed revision to the WNP-2 Technical Specification is acceptable.
- 3. 0 ENVIRONMENTAL CONS IDERATION This amendment involves a change in the installation and use of a facility component located within. the restricted area as defined in 10 CFR Part 20 and changes in surveillance requirements.
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 cumula-tive 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.
Accord-ingly, this amendment 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 environmental assessment need be prepared in connection with the issuance of this amendment.
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4.0 CONCLUSION
The Commission made a proposed determination that the amendment involves no significant hazards consideration which was published in the Federal Re ister (51 FR 8603) on March 12, 1986, and consulted with the state of as langton.
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 and 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:
Gerald B. Zwetzig, Region V
Dated:
Hay 13, 1986
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