GO2-86-732, Supplemental Application for Amend to License NPF-21, Revising Tech Specs Re ECCS Actuation Instrumentation & Motor Operated Valve Thermal Overload Protection
| ML17278A965 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 08/04/1986 |
| From: | Sorensen G WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | Adensam E Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17278A966 | List: |
| References | |
| GO2-86-732, TAC-59820, NUDOCS 8608130369 | |
| Download: ML17278A965 (7) | |
Text
ACCESSION NBR:
FAC IL: 50-397 AUTH. NANE SORENSENi Q C
RECIP. NAl'IE ADENSAN> E. Q.
P REQUL Y INFGRl'1ATION DISTR IBUT SYSTEI'1 (R IDS) 8608130369 DOC. DATE: 86/08/04 NOTARIZED: YES DOCKET 0 WPPSS Nuclear Pv ogecti Unit 2i Washington Publi c Powe 05000397 AUTHOR AFFILIATION Washington Public Powev Supplg Sgstem RECIPIENT AFFILIATION BWR Pv object Div ectorate 3
SUBJECT:
Supplemental application for amend to License NPF-2ii revising Tech Specs v e ECCS actuation instv'umentation 5
motov'pev ated valve thermal overload pv'otection.
DISTRIBUTION CODE:
A001D COPIES RECEIVED: LTR ENCL SI ZE:
TITLE:
OR Submittal:
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Washington Public Power Supply System P.O. Box 968 3000 George Washington Way Richland, Washington 99352 (509) 372-5000 August 4, 1986 G02-86-732 Docket No.
50-397 Director of Nuclear Reactor Regulation Attn:
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:
NUCLEAR PLANT NO.
2 OPERATING LICENSE NPF-21, REQUEST FOR TECHNICAL SPECIFICATION AMENDMENT TO REFLECT REACTOR CORE ISOLATION COOLING (RCIC)
SYSTEM DOWNGRADE RESULTING FROM MODIFICATIONS TO AUTOMATIC DEPRESSURIZATION SYSTEM (ADS) LOGIC, SUPPLEMENTAL INFORMATION
References:
1)
Letter, G02-85-694, G.
C. Sorensen (SS) to W.
R. Butler (NRC),
Same Subject, dated October 4, 1985 2)
- Letter, G02-85-817, G.
C. Sorensen (SS) to E.
G.
Adensam (NRC),
Same Subject, dated December 5,
1985 The referenced letters discuss the background to and request for the downgrade of the RCIC.
They also request several changes to plant Technical Specifica-tions reflecting the downgrade of the RCIC.
We inadvertently did not include in the proposed changes to the Technical Specification the attached modifications to Limiting Condition for Operation (LCO) 3.3.3, nor a similar change to LCO 3.5. 1.
We request that they be included as a part of the Technical Specification amendment request contained in the references.
We have also included pages 3/4 8-26 and 8-27 (Table 3.8.4.3-1).
The RCIC valves being deleted from this Table are not automatically actuated contain-ment boundary valves, nor would their. failure impact another safety system.
The valves are within the RCIC System boundary only.
Since RCIC is no longer relied upon to perform a safety-related function, it is appropriate to remove them from the Table.
Valves RCIC-V-8, 63, and 76 are still relied upon to perform an automatic containment isolation function so they are being left in the Table.
8b081303b9 8b0804 I PDR ADOCK 05000397 P
'I
E.
G.
Adensam Page Two August 4, 1986 REQUEST FOR TS AMEND. TO REFLECT RCIC SYSTEM DOWNGRADE RESULTING FROM MODS.
TO ADS LOGIC, SUPP.
INFO.
These additional changes are bounded by the 10 CFR 50.59 analysis previously performed (no unreviewed safety questions) as well as the analysis required by 10 CFR 50. 92 (no significant hazards determination).
They are needed so that all plant Technical Specifications reflect the RCIC downgrade and to avoid the need for a future conforming change to Technical Specifications.
The Staff had also asked the Supply System to provide additional information to demonstrate why the time allowed in Action c. 1 (14 days) should not be changed to coincide with that allowed in a. 1 or b. 1 (7 days).
The Supply System feels that this is clearly provided for in the Bases for 3/4.5. 1 and 3/4.5.2 (pages 8 3/4 5-1 and 5-2).
The Bases clarifies that with the HPCS system i~operable, adequate core cooling is assured by the OPERABILITY of the redundant and diversified ADS, and both the LPCS and LPCI systems.
Additionally, the RCIC system, a system for which no credit is taken in the safety analysis, will automatically provide makeup at reactor operating pressures on a reactor low water level condition.
It fur ther emphasizes that the HPCS out-of-ser vice period of 14 days is based on the demonstrated OPERABILITY of redundant and diversified low pressure core cooling systems.
On that basis, no change to the out-of-service time is justified.
Because the modifications attached to this letter are a conforming change initiated by the Technical Specification modifications previously requested and noticed in the'Federal '~Re'ister (51 Fed.
Reg.
3721, 1986), the Supply System understands that the public notice requirements of 10 CFR 50.91 and 50.92 have been satisfied.
Therefore, this modification can proceed without any undue delay.
If you have any questions, please contact Mr. P.
L. Powell, Manager, WNP-2 Licensing.
Very truly yours, G.
C.
So ensen, Manager Regulatory Programs HLA/tmh Attachment cc:
JO Bradfute -
NRC C
Eschels -
NRC RV E
Revell -
BPA NS Reynolds -
BLCP8R NRC Site Inspector
STATE OF WASHINGTON
}
).
COUNTY OF BENTON
Subject:
RCIC Down rade I, G.
C.
- SORENSEN, being duly swor n, subscribe to and say that I am the
- Manager, Regulatory Programs, for the WASHINGTON PUBLIC POWER SUPPLY SYSTEM, the applicant herei'n; that I have full authority to execute thi's 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.
OATE 4 4MC>C(>7
, 1986 G.
C.
S9R NSEN, Manager Regulatory Programs 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'igned the same as his free act and deed for the uses and purposes therein mentioned.
GIVEN under my hand and seal this day of
, 1986.
Notary Pub ic in and for the State of Washington Residing at
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