GO2-86-147, Revised Application for Amend to License NPF-21,modifying 860117 Request Re Primary Containment Isolation Valves by Incorporating Sys Upgrading & Corrections/Additions Concerning Excess Flow Check Valves
| ML17278A601 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 02/18/1986 |
| From: | Sorensen G WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | Adensam E Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17278A602 | List: |
| References | |
| GO2-86-147, TAC-60953, NUDOCS 8602240267 | |
| Download: ML17278A601 (10) | |
Text
REGULATOR
%FORMATION DISTRIBUTION S
'EM <RIDS)
ACCESSION NBR: 8602240267 DOC. DATE: 86/02/18 NOTARIZED:
YES DOCKET 0 FACIL: 50-397 NPPSS Nuclear Prospect>
Unit 2i Nashington Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION SORENSENg Q. C.
Wash ing ton Pub Ii c Power Sup p 1 g Sg stem REC IP. NAME REC IP IENT AFFILI*TION ADENSAM> E. Q.
BWR Prospect Directorate 3
SUBJECT:
Revised application for amend to License NPF-21'odifying 860117 r'equest re primary containment isolation valves bg incorporating sos upgrading 0 corrections/additions concerning excess Plow check valves.
DISTRIBUTION CODE:
A001D COPIES RECEIVED: LTR ~ ENCL ~
SIZE:
TITLE:
OR Submittal:
General Distribution NOTES:
RECIPIENT ID CODE/NAME BNR ADTS HNR EH HNR FOH HNR PSB COPIES LTTR ENCL 1
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REC IP lENT ID CODE/NAME HMR PD3 PD 01 HNR EICSH BRADFUTE> J BNR RSB COPIES LTTR ENCL 5
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INTERNAL: ACRS ELD/HDS2 N
8 ILE EXTERNAL: 24X LPDR NSIC OV AB 04 03 05 6
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1 ADM/LFMH NRR/DHFT/TSCB NRR/ORAS RQN5 EQSQ BRUSKE> S NRC PDR 02 1
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TOTAL NUMBER OF COPIES REQUIRED:
LTTR 30 ENCL 26
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Washington Public Power Supply System P.O. Box 968 3000 George Washington Way Richland, Washington 99352 (509) 372-5000 February 18, 1986 G02-86-147 Docket No. 50-397 Director of Nuclear Reactor Regulation Attention:
Ms. E.
G. Adensam, Project Director BWR Project Directorate No.
3 Division of BWR Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Ms. Adensam:
Subject:
Reference:
NUCLEAR PLANT NO.
2 OPERATING LICENSE NPF-21, REQUEST FOR AMENDMENT TO TECHNICAL SPECIFICATIONS (TABLE 3.6.3-1),
MODIFICATION OF Letter, G02-86-083, G.C.
Sorensen (SS) to E.G.
Adensam (NRC),
"Request for Amendment to Technical Specifications (Table 3.6.3-1)," dated January 17, 1986.
In accordance with the Code of Federal Regulations, Title 10, Parts 50.90 and 2.101, the Supply. System hereby requests an amendment to the WNP-2 Technical Specifications.
The referenced
- letter, in part, requested a
number of amendments to the Primary Containment Isolation Valves (Table, 3.6.3-1).
This letter modifies the referenced request in order to incorporate system upgrading and incorporation of corrections/additions regarding excess flow check valves.
Specifically, the following additional changes are requested:
~23 2.1-33 3/46-24 An upgrade of the H202 system as required by WNP-2 License Condition 816 is being implemented to meet Reg.
Guide 1.97 requirements.
The system upgrade requires the relocation of the sample return points and therefore, a
redesignation of the isolation valves (from penetrations X-72b and X-73c to X-78a and X-42c).
The upgraded H~Op system will be fully operational when WNP-2 comes to power following the
/936 spring outage.
8602240267 8602i839 p
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G. Adensam Page Two February 18, 1986 REQUEST FOR AMENDMENT TO TECH.
SPECS.
(TABLE 3.6.3-1),
MODIFICATION OF The Supply System has reviewed this change per 10 CFR 50.92 and determined that it does not:
1)
Involve a significant increase in the probability or consequences of an accident previously evaluated because the primary containment design will not change.
Only the configuration will be altered using the same valves.
2)
Create the possibility of a new or different kind of accident from any accident previously evaluated because the number of excess flow check valves is not increased.
The existing valves are only being relocated to accommodate an improved system design.
3)
Involve a significant reduction in the margin of safety because instrument return lines are designed to the same criteria used in the original return line designs.
Chan e No.
2 - Pa e 3/4 6-25 The referenced letter requested that excess flow check valve PI-EFC-XB, installed on the LPCS-dpI-10 line, be added to Table 3.6.3-1.
Although the valve had not been specifically listed in the table, it had been included in the excess flow check valve surveillance program.
This change withdraws our request to have PI-EFC-X8 added to the table and requests that excess flow check valves PI-EFC-X12A, B, and C also be deleted from Table 3.6.3-1.
The design function of instrumentation RHR-dpIS-9A, B, and C and LPCS-dpI-10 have been deleted from the system.
A more positive indication of RPV pressure is
- used, thus allowing valve actuation in accordance with ECCS response times while minimizing the potential of over pressurization of the upstream piping.
Since the instruments and excess flow check valves are no longer used, it has been decided to remove them and their associated pipe/tubing from the plant.
With these valves installed, testing of the excess flow check valves is required as part of the primary containment isolation valve testing requirements.
To eliminate the testing of these
- valves, the instrument lines will be capped at the root valves and the instruments removed from the plant thereby eliminating valves PI-EFC-X12A, B, C and X8.
The Supply System has reviewed this change per 10 CFR 50.92 and determined that it does not:
1)
Involve a significant increase in the probability or consequences of an accident previously evaluated because elimination of the change replaces an active component with positive design configuration.
Unnecessary instrumentation will decrease the probability of an occurrence or the consequence of an accident.
lJ N
E.
G. Adensam Page Three February 18, 1986 RE(}UEST FOR AMENDMENT TO TECH.
SPECS.
(TABLE 3.6.3.1),
MODIFICATION OF 2)
Create the possibility of a new or different kind of accident from any accident previously evaluated because removal of these will not affect the operati on of the systems.
3)
Involve a significant reduction in the margin of safety because the configuration will be typical of other pl ant process piping test connections.
The Supply System has reviewed these changes per 10 CFR 50.59 and determined that no unreviewed safety questions will result from implementation of the changes discussed in this amendment.
This change has been reviewed and approved by the WNP-2 Plant Operations Committee and the Supply System Corporate Nuclear Safety Review Board.
In accordance with 10 CFR 50.91, the State of Washington has been provided a
copy of this letter.
Should you have any questions regarding this matter, please contact Mr. P.L. Powell, Manager, WNP-2 Licensing.
Very truly yours, G.
C. Sorensen, Manager Regulatory Programs SIS/sir Attachments cc:
JO Bradfute -
NRC C
NRC RV E Revel - BPA NS Reynolds - BLCP8R NRC Site Inspector
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STATE OF WASHINGTON
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County of Benton
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Subject:
I, G. C.
SORENSEN, being duly sworn, subscribe to and say that I am the
- Manager, Regulatory Programs for the WASHINGTON PUBLIC POWER SUPPLY
- SYSTEM, the applicant herein; that I have full authority to execute this oath; that I have reviewed the foregoing; and that to the best of my knowledge, information and belief the statements made in it are true.
DATE
, 1986
- rensen, anager Regulatory Programs
, 1986.
On this day personally appeared before me G. C. Sorensen to me known to be the individual who executed the foregoing instrument and acknowledge that he signed the same as his free act and deed for the uses and purposes therein mentioned.
GIVEN under my hand and seal this -Ig day of," K~4~
otary u
ic in an or t e State of Washington Residing at
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