ML17278B099

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Application for Amend to License NPF-21,revising Tech Spec Tables 3.3.7.5-1, Accident Monitoring Instrumentation & 4.3.7.5-1, Accident Monitoring Instrumentation... to Allow Adequate Time for Staff Review & Approval.Fee Paid
ML17278B099
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 11/18/1986
From: Sorensen G
WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To: Adensam E
Office of Nuclear Reactor Regulation
Shared Package
ML17278B100 List:
References
GO2-86-1027, TAC-63934, TAC-64838, TAC-66889, NUDOCS 8612010062
Download: ML17278B099 (9)


Text

ACCESSlON NBR:

FAC IL:50-397 AUTH. NAl'fE SORENSENE G. C.

RECIP. NANE ADENSANiE. ('.

REGULA Y

FORNATION DISTRIBUTI EN (RIDS) 8612010062 DOC. DATE: 86//}8 NOTARIZED: YES DOCKET 0 WPPSS Nuclear Progecti Unit 2i Washington Public Powe 05000397 AUTHOR AFFILIATION Washington Public Power Supply System REC IPIENT AFFILIATION BWR Prospect Directorate 3

SUBJECT:

Application for amend to License NPF-2}irevising Tech Spec Tables 3, 3. 7. 5-}> "Accident Monitoring Instrumentation"

4. 3. 7. 5-}i "Accident Monitoring Surveillance Requirements" to al low adequate time for staf f review 5 approval. Fee p id.

DISTRIBUTION CODE: AOOSD COPIES RECEIVED, LTR I ENCL J SIZE TITLE: OR/Licensing Submittal: Supp l 1 to NUREO-0737(Generic Ltr 82-33) NOTES: RECIPIENT ID CODE/NANE BMR ADTS BWR EICSB BMR PD3 LA BRADFUTE J BWR RSB INTERNAL ADN/LFNB NRR BWR ADTS NRR PWR-B ADTS NR SR EC EXTERNAL: LPDR NSIC COPIES LTTR ENCL 1 1 2 2 1 1 1 1 1 0 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME BWR EB BWR FOB BWR PD3 PD BWR PSB IE/DEPER/EPB NRR PAULSONi W 'RR/DSRQ ESPRIT NRR/DSRQ/RSIB Rl'N5 NRC PDR COPIES LTTR ENCL 1 } 7 7 1 3 3 1 1 1 1 1 TOTAL NUj')BER OF COPIES REQUIRED: LTTR 31 ENCL 30

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~ 0 gp 0 ~ WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ 3000 George Washington Way ~ Richland, Washington 99352 November 18, 1986 G02-86-1027 Docket No. 50-397 Director of Nuclear Reactor Regulation Attn: 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 3.3.7.5-1 ACCIDENT MONITORING INSTRUMENTATION AND TABLE 4. 3. 7. 5-1 ACCIDENT MONITORING SURVEILLANCE REQUIREMENTS License Condition 16, Attachment 2, Item 3b to WNP-2 Operating License NPF-21 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 subject Technical Specification Tables (see attached).

This request is submitted in anticipation of work to be started and completed during the spring 1987 refueling outage. The intent is to allow adequate time for staff review and approval and arrange for release of the changed specifi-cation upon completion of'he modification. The referenced license condition states: "The licensee shall implement (installation or upgrade) require-ments of Regulatory Guide 1.97, Revision 2, for flux monitoring prior to startup following the second refueling outage." Accordingly, the Supply System is in the process of procuring equipment to meet this schedule and satisfy the license condition. The WNP-2 Technical Specifications (Tables 3.3.7.5-1 and 4.3.7.5-1) currently reflect three instruments, APRM/IRM/SRM, rather than the single wide range monitors being installed. As such, it is necessary to obtain the requested technical specification change. 8612010062 861118 PDR ADOCK 05000397',' PDR

~ 0 A II

~ 0 E. G. Adensam Page Two November 18, 1986 REQUEST FOR AMEND. TO TS TABLE 3.3. 7. 5-1, ACCIDENT MONITORING INSTRU. AND TABLE 4. 3. 7. 5-1, ACCIDENT MONITORING SURVEILLANCE REQUIREMENT Additionally with the redundancy provided by the current flux monitoring devices the action statement for wide range monitors should be changed from "80" to "81" ~ Under action statement 81 the alternate method of monitoring to be used should the number of operable channels be less than the minimum would be the existing

APRM, IRM and SRM monitors.

This condition is similar to other instruments listed in Table 3.3.7.5-1. For example: Primary Containment Gross Radiation Monitors, Effluent Noble Gas Radiation Monitor, Reactor Building Post LOCA Grab Sample and so forth. The Supply System has reviewed this request per 10 CFR 50.59 and 50.92 and has determined that it does not represent an unreviewed safety ques-tion or significant hazard and does not: 1) Involve a significant increase in the probability or consequences of an accident previously evaluated because the equipment being installed will not provide input to any safety systems relied on in any of the licensing bases accident analyses. Hence, it can not significantly increase the probability of a previously evaluated accident. The change in action statements does not significantly increase the proba-bility or consequences of an accident previously evaluated because the redundant

APRM, IRM and SRH monitors presently utilized in the techni-cal specifications will be available should the wide range monitors be declared inoperable.

The availability of these monitors given the remote possibility of the wide range monitors being inoperable ensures that the change in action statements does not significantly increase. the probability or consequences of an accident previously evaluated. 2) Create the possibility of a new or different kind of accident than previously evaluated. because the equipment provides monitoring only and merely provides another display in addition to the existing devices currently relied upon that indicate neutron flux or power levels. The change in action statements does not create the possi-bility of a new or different kind of accident because the equipment provides a monitoring function. only and has adequate redundancy with . the existing

APRM, IRH and SRH monitors so that no new or different kind of accident is credible.

0 ~ ~ ~

E. G. Adensam Page Three November 18, 1986 RE(UEST FOR AMEND. TO TS TABLE 3. 3. 7.5-1, ACCIDENT MONITORING INSTRU. AND TABLE 4.3.7.5-1, ACCIDENT MONITORING SURVEILLANCE REQUIREMENTS 3) Involve a significant reduction in a margin of safety because no design safety margins are jeopardized. As stated above, this equipment provides a passive monitoring function only and does not interact actively in any plant safety related system. As

such, safety margins will not be affected.

The change in action statements does not involve a significant reduction in a margin of safety because the redundant monitors provide adequate backup given the remote possibility that the wide range monitors become inoperable. The existing monitors have been adequate over the period since licensing (3 years), given this, should the wide range monitors become inoperable the short period for which the redundant-monitors would be utilized does not introduce a signi-ficant reduction in a safety margin. This technical specification change has been reviewed and approved by the WNP-2 Plant Operations Coomittee and the Supply System Corporate Nuclear Safety Review Board. In accordance with 10 CFR 170. 21, an application fee of One hundred fifty dollars ($ 150.00) accompanies this request. In accordance with 10 CFR 50. 91, the State of Washington has been provided a copy of this letter. Should you require any further information or assistance to aid in evalua-ting this request, please contact Hr. P. L. Powell,

Manager, WNP-2 Licensing.

Very truly yours, G. C. S

ensen, Manager Regulatory Programs PLP/bk Attachment cc:

JO Bradfute - NRC JB Hartin - NRC RY C Eschels - EFSEC E Revell - BPA NS Reynolds - BLCP&R NRC Site Inspector

STATE OF WASHINGTON ) COUNTY OF BENTON Accident Monitoring Instrumentatio

Subject:

5 Accident Monitoring Surveillance equiremen s I, G. C.

SORENSEN, being duly sw'orn, 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 /Z 4' 1986 G. C. S+0 NSEN, Manager 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 acknowledged 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 1 ~ day of 'E otary Pub ic in an for t e State of Washington Residing at

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