ML17278A865
| ML17278A865 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 05/23/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17278A864 | List: |
| References | |
| TAC-60952, NUDOCS 8605300472 | |
| Download: ML17278A865 (10) | |
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR 'REACTOR REGULATION SUPPORTING AMENDMENT NO.
27 TO FACILITY OPERATING LICENSE NO.
NPF-21 WASHINGTON PUBLIC POWER SUPPLY SYSTEM WPPSS NUCLEAR PROJECT NO.
2 DOCKET NO. 50-397
1.0 INTRODUCTION
By letter dated January 17, 1986, Washington Public Power Supply System reouested an amendment to the Technical Specifications, Table 3.8.4.3-1, Motor Operated Valves Thermal Overload Protection, for WPPSS Nuclear Project No.
2 (WNP-2).
The following revisions were requested:
- 1. Modification of Table 3.8.4.3-1, Motor Operated Valves Thermal Overload Protection.
- 2. Addition of various Auxiliary Steam and Fuel Pool Coolinq System valves to Table 3.8.4.3-1.
Motor-operated valves equipped with thermal overload protection devices are used in valve motors for safety systems and their auxiliary supporting systems.
Requlatory Guide 1. 106, "Thermal Overload Protection for Electric Motors on Motor-Operated Valves",
recommends bypassinq thermal overload devices during accident conditions, or selecting the setpoints for the thermal overload in a manner that precludes spurious trips.
In the WNP-2 design, motor thermal overloads for Class 1E motor-operated valves are selected two sizes larger than the normally selected thermal overload.
This approximates 140% of motor full load current.
2.0 DISCUSSION AND REVIEW
- 1) The licensee proposed a chanqe to update and correct Table 3.8.4.3-1, Motor Operated Valves Thermal Overload Protection.
The current Table contains listings for valves that are not safety related; therefore, their listing is not necessary according to requirements of Regulatory Guide 1. 106.
Also the licensee found that two valves that should have been included in the Table were omitted.
The "B" valves for each of two pairs of valves were inadvertently omitted although the "A" valves for each pair were included.
Thus, the proposed
- changes, deletion of non-safety related valves from Table 3.8.4.3-1 and addition of two safety related valves to the Table, are acceptable.
Further with respect to the omitted "B" valves the licensee
- asserts, and the staff agrees, that the omission does not impact a Limiting Condition for Operation (LCO) because the Surveillance Requirements specify that performance of Channel Calibrations must be, performed on a representative 8605300472 860523 PDR ADOCK 05'00039i7:
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2 sample of at least 25% of all thermal overloads for the valves listed in Table 3.8.4.3-1.
The licensee assures that, despite the omission, such calibrations have been performed and that the surveillance require-ment has been satisfied.
Therefore, the omission of the two "B" valves did not compromise safety requirements.
- 2) Because of Equipment gualification concerns, the licensee proposed a
chanqe to add valves AS-V-68A and AS-V-68B to Table 3.8.4.3-1.
This isolation valve installation was made to reduce the possibility of Reactor Building area temperature exceeding equipment qualification temperature limits.
The auxiliary steam line leak detection system consists of redundant temperature
- sensors, temperature
- switches, and isolation valves AS-V-68A and AS-V-68B.
When any one of the temperature elements detects abnormally high temperatures, the logic circuit actuates the closure of auxiliary steam line isolation valves AS-V-68 A and B and provides an audible alarm in the main control room.
Because the two
- valves, AS-V-68A and AS-V-68B, perform this safety function, their addi-tion to the table is acceptable.
- 3) The Fuel Pool Cooling (FPC) system valves are added to the table as a
result of the system upgrade to safety-related as required by commit-ments made regarding 10 CFR 50.55(e)
Reportable Deficiency - Condition No.
44 (1).
Valves FPC-V-172, - 173 and - 184 provide auto-isolation (closing) between the Seismic Category I portion of the FPC system and its Seismic Category II filter-demineralizers.
Valves FPC-V-181A and 181B provide suction isolation for the FPC system's main circulation pumps.
Valve FPC-V-175 provides a Class 1 auto-bypass to the FPC system's flow control valve FPC-FCV-1.
The licensee has stated that the thermal overload protection system for these valves is designed in accordance with the approved WNP-2 design criteria for motor-operated safety related valves.
Thus, the addition of these motor operated valves to the FPC system is acceptable.
3.0 ENVIRONMENTAL CONSIDERATION
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 to 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 findinq that this amendment involves no siqnificant 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 '51.22(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 Register (51 FR 15416) on April 23, 1986, and consulted with the state of Mashinqton.
No public comments were received, and the state nf Mashinqton did not have any comments.
The staff has concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endanqered bv operation in the pronosed
- manner, and (21 such activities will be conducted in compliance with the Commission's regula-tions and the issuance of this amendment will not be inimical to +he common defense and security or to the health and safety of the public.
Principal Contributor:
Sang C.
- Rhow, NRR Dated:
May'23, 1986
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ANENDYiENT NO. 27 TO FACILITY OPERATING LICENSE NO. NPF-21 WPPSS Nl!CLEAR PROt>FCT NO.
2 DISTRIBUTION:
MRooket-No
. 50-397 NRC P0R Local PDR PRC System NSIC BWD-3 r/f
.)Bradfute (2)
. EHylton (1>
EAdensam
- Attorney, OELD CNiles RDiggs
.1Partlow EJordan BGrimes LHarmon TBarnhar t (4)
FROM:
Elinor G Adensam, Director BWR Project Directorate No.
3 Division of BWR Licensing May 23, 1986 MEMORANDUM FOR:
Sholly Coordinator DIS UTION:
c et No.
0-397 BWD-3 r/f EAdensam JBradfute EHylton JScinto SUBJECT' RE(}UEST FOR PUBLICATION IN BI-WEEKLY 'FR NOTICE - NOTICE OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE Washinqton Public Power Su 1
- System, Docket No. 50-397, WNP-2, Richland,
~ashincaton Dates of a lication for amendment:
January 17,
- 1986, and February 18, 1986 Brief descri tion of amendment:
This action amends the WNP-2 Technical Specification Table 3.6.3-1, "Primary Containment Isolation Valves" to:
(1) reflect corrections and additions to and deletions from the Excess Flow Check Val've listings, Traversing Incore Probe System valve listings, Residual Heat Removal System valve listings and equipment qualification limits; (2) reidentify certain valves in accordance with current Supply System practices; (3) add valves previously omitted; (4) provide clarification to notes in the table; (5) correct typographical errors; and (6) delete maximum isolation time listings for valves not performing an automatic containment isolation function.
Date of Issuance:
May 23, 1986 Effective Date:
May 23, 1986 Amendment No:
26 Facilit 0 eratin License No. NPF-21:
Amendment revises the Technical Specifications.
Date of Initial Notice in the Federal'egister:
April 23, 1986 (51'FR 15416)
The Commission's related evaluation of the amendment is contained in a Safety Evaluation dated May 23, 1986.
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1 No significant hazards consideration comments received:
No Local Public Document Room Location:
Richland Public Library, Swift and Northgate Streets,
- Richland, Washington 99352.
/S/
Elinor G. Adensam, Director BWR project Directorate No.
3 Division of BWR Licensing L
D-3:DBL lton/hmc
/~ /86 BWD-3:DBL JBradfute 5/(z./86 D-3:DBL EAd~am 5/i C /86
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