ML17278A860
| ML17278A860 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 05/23/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17278A859 | List: |
| References | |
| TAC-60953, NUDOCS 8605300363 | |
| Download: ML17278A860 (12) | |
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UNITED STATES NUCWcAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO.
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 letters dated January 17,
- 1986, and February 18, 1986, the Mashinqion Public Power Supply System (WPPSS, the Supply System or the licensee}
requested a number of revisions to Table 3.6.3-1 (Primary Containment Isolation Valves) of the MNP-2 Technical Specifications.
One of the revisions involves a manual isolation valve in the Fuel Pool Cooling system that was converted to an automatic isolation valve.
That request was granted in a previous amendment to the WNP-2 Technical Specifications.
The remaining requests are the subject of this safety evaluation.
2.0 EVALUAT?ON The MNP-2 license revisions addressed in this evaluation involve changes to the Technical Specifications for one or more of the following reasons:
a.
System modification(*) that eliminated the need for a valve previously used, with FSAR updates reflecting change; b.
System modification(*l that added a valve; c.
System modification(*) that changed the function or operation of a valve; d.
Changes in the scheme used to name valves so that the Table 3.6.3-1 names are consistent with the names used by Supply System plant and engineering personnel; e.
Correction of errors originally included in the Table and not pre-viously found; f.
Explanation footnote added; and g.
Ordering of valves within the Table to reflect a more appropriate system name or desiqnation.
(*)
System modifications were accomplished on the basis of 10 CFR 50.59 reviews performed by the Supply System.
8605300363 860M3 PDR ADOCK 05000397 P
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Following is a list of the valves for which chanqes were requested.
The list includes;
- 1) the new or current name for each valve; 2) the old name for those valves where the name has changed; 3l a brief description of the chanoe; 4) a letter desiqnation from the list above indicatinq the reason for the change; and 5) a remark, if appropriate.
Valves that have been removed from the system or from the table are listed in the Column 2.
REQUESTED CHANGES TO WNP-2 TECHNICAL SPECIFICATIONS Table 3.6.3-1 Primary Containment Isolation Valves 1
Valve Name ling 2
Valve Name 3
Chanoe 4
Reason 5
Remarks TIP-V-1 TIP-V-2 TIP-V-3 TIP-V-4 TIP-V-5 TIP-V-6 TIP-V-7 TIP-V-8 TIP-V-9 TIP-,V-10 TIP-V-11 TIP-V-6 TIP-V-7 TIP-V-8 TIP-V-9 TIP-V-10 TIP-V-12 TIP-V-1 TIP-V-2 TIP-V-3 TIP-V-4 TIP-V-5 New name New name New name New name New name New name New name New name New name New name New name d
d d
d d
dd,f d,f d,f d,f d,f RWCU-V-1 TIP-V-11 Valve removed from Table Footnote
(,i) added to Maxi-mum Isolation Time e
Originally included in error.
The valve is not a Containment Isolation Valve.
f Closure time reauired to meet 10 CFR 100 limits.
Alamo subiect to other closure time limits that could be more restrictive.
RWCU-V-4 RCIC-V-8 RCIC>>V-63 Footnote (i) added to Maxi-mum Isolation Time Footnote (j) added to Maxi-mum Isolation Time Footnote (,i) added to Maxi-mum Isolation Time f
Closure time required to meet 10 CFR 100 limits.
Also subiect to other closure time limits that could be more restrictive.
f Closure time reouired to meet 10 CFR "100 limits.
Also subiect to other closure time limits that could be more restrictive.
f Closure time required to meet 10 CFR 100 limits.
Also subject to other closure time limits that could be more restrictive.
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Valve Name W
Valve Name
~Chan e
Reason Remarks RCIC-V-64 PI-EFC-X29d PI-EFC-X29f PI-EFC-X30a PI-EFC-X30f PI-EFC-X42c P I-EFC-X42f PI-EFC-X69f PI-EFC-X66 PI-EFC-X67 PI-EFC-X78a PI-EFC-X82b PI-EFC-X84a PI-EFC-X86A PI-EFC-X86B PI-EFC-X87A PI-EFC-X87B PI-EFC-X119 CAS-V-730 RHR-'V-124A RHR-V-1248 RHR-V-125A RHR-V-1258 RCIC-V-742 PI-EFC-X29b/d PI-EFC-X29e/f PI-EFC-X30a/c PI-EFC-X30d/f PI-EFC-X73c PI-EFC-X4?e/f PI-EFC-X69d/f P I-EFC-X72b CAS-V-453 Changed to
- manual, locked closed operation New name New name New name New name Moved New name New name Moved Moved Moved Moved Moved Moved Moved Moved Moved Moved Valve added Removed from Table Moved Moved Moved Moved Footnotes added c
Automatic actuation not needed because. operational mode of its system is not used or needed.
Safety function of containment isolation remains unchanged.
b Manual, locked closed valve reolaces check valve CAS-CVX-82e.
Safety function of containment isolation remains unchanged.
Replaced by CAS-V-730; no longer needed for containment isolation.
Previous Table location in error.
Previous Table location in error.
Previous Table location in error.
Previous Table location in error.
f No change in requirement; information only.
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4 Valve Name
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BEg Val ve Name Chasse Reason Remarks RCIC-V-68 RCIC-B-68 RHR-RV-55A RHR-RV-55R RHR-RV-95A RHR-RV-95B Typographical error Removed from system Removed from system Removed from system Removed from system a
Replaced with blind flange.
a Replaced with blind flange.
a Replaced with blind flange.
a Replaced with blind flange.
PI-EFCX-72f PI-EFCX-73e Added to table e
Previously omitted from Table in error.
Added to table e
Previously omitted from Table in error.
In addition, the licensee proposed to eliminate the "Maximum I.solation Times" for the valves identified in Sections b, c, and d of Table 3.6.3-1.
These valves are remote manual valves and are either normally closed, or have one or more check valves in the line 'between the valve and the reactor.
A review of other plants'echnical Specifications indicate'that similar valves do not have maximum allowable closure times identified in their Technical Specifications.
Furthermore, the valves are part of the ASME Section XI inservice testing program.
As part of this program, there is a maximum closure time limit as part of the testing.
- Thus, we conclude that the elimination of the maximum closure times for these valves in the Technical Specifications are acceptable.
On the basis of this evaluation and the evaluations indicated in the "Reason" and "Remarks" columns of the above table, the staff finds that the changes indicated in the above table as well as the removal of time limits for valves that do not receive automatic isolation signals are acceptable.
3.0 ENVIRONMENTAL CONSIDERATION
This amendment involves a change in the installation and use of a facilitv component located within the restricted area as defined in 10 CFR Part 20
"'nd changes in surveillance requirements.
The staff has determined that this amendment involves no siqnificant 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 previouslv 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 eligibilitycriteria 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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'f If 4.n CDNCLijSioN The Commission made a proposed determination, that the amendment involves no significant hazards consideration which was published in the Federal Register (51 FR 15416) on April 23, 1986, and consulted with the state of Washington.
Nn 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 he endanqered by operation in the Prooosed
- manner, and (2) such activities will be conducted in compliance with the Commission's requla-tions and the issuance of this amendment will not be inimical to the common defense and security nr to the health and safety of the Public.
Principal Contrihutors:
John N. Ridgely, NRR Peter
Nay 23, 1986
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AMENDMENT NO, 26 TO FACILITY OPERATING LICENSE NO. NPF-21 WPPSS NUCLEAR POJECT NO.
2 DISTRIBUTION:
.'Docket No.-50-397- ~
NRC PDR Local PDR PRC System NSIC BWD-3 r/f JBradfute (2)
EHylton (1)
EAdensam
- Attorney, OELD CMiles RDigqs JPartlow EJordan BGrimes LHarmon TBarnhart (4)
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