GO2-85-817, Application for Amend to License NPF-21,revising Tech Spec 3/4.3.5, RCIC Sys Actuation Instrumentation, Reflecting Downgrade Resulting from Mods to Automatic Depressurization Sys Logic

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Application for Amend to License NPF-21,revising Tech Spec 3/4.3.5, RCIC Sys Actuation Instrumentation, Reflecting Downgrade Resulting from Mods to Automatic Depressurization Sys Logic
ML17278A497
Person / Time
Site: Columbia 
Issue date: 12/05/1985
From: Sorensen G
WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To: Adensam E
Office of Nuclear Reactor Regulation
Shared Package
ML17278A498 List:
References
GO2-85-817, TAC-59820, NUDOCS 8512100099
Download: ML17278A497 (8)


Text

REGULATORY INFORNATION DISTRIBUTION SYSTEN (RIDS)

ACCESSION NBR: 85}2}00099 DOC. DATE: 85/12/05 NOTARIZED: YES DOCKET FACIL:50-397 WPPSS Nuclear Progecti Unit 2>

Washington Public Poee 05000397 AUTH. NANE AUTHOR AFFILIATION SORENSEN> G. C.

Washington Public Power Supply System RECIP. NANE RECIPIENT AFFILIATION ADENSANiE. Q.

BWR Prospect Directorate 3

SUBJECT:

Application for amend to License NPF-2}irevising Tech Spec 3/4. 3. Si "RCIC Sgs Actuation Instrumentati on. " reflecting dotongrade resulting from mods to automatic depressurization sos logic.

DlSTRIBUTION CODE:

A00}D COPIES RECEIVED: LTR ENCL SIZE:

TITLE:

OR Submittal:

General Distribution NOTES:

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TOTAL NUMBER OF COPIES REQUIRED:

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Washington Public Power Supply System 3000 George Washington Way P.O. Box 968 Richiand, Washington 99352-0968 (509)372-5000 December 5,

1985 G02-85-817 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:

NUCLEAR PLANT NO.

2 OPERATING LICENSE NPF-21, REQUEST FOR TECHNICAL SPECIFI-CATION AMENDMENT TO REFLECT REACTOR CORE ISOLATION COOLING (RCIC)

SYSTEM DOWNGRADE RESULTING FROM MODIFICATIONS TO AUTOMATIC DEPRESSURIZATION SYSTEM (ADS) LOGIC, SUPPLEMENTAL INFORMATION

References:

1) 2)

, 3)

Letter, G02-83-660, G.

C. Sorensen (SS) to A. Schwencer (NRC}, dated July 26, 1983 Amendment No.

11 to OL NPF-21, dated June 25, 1985 Letter, G02-85-694, G.

C. Sorensen (SS) to W.

R. Butler (NRC}, dated October 4, 1985 The referenced letters discuss the background to and request for the'down-grade of the Reactor Core Isolation Cooling System.

This letter supplies additional information about the proposed technical specification amendment and addresses questions asked by Messrs.

Br adfute and Hodges during October 25, November 5, and.November 18, 1985 phone conversations on this subject.

In those phone conversations, additional clarification was requested on three topics.

The first was a concern for minimizing the potential for spurious automatic actuations of the RCIC system.

To address this, the marked up Technical Specification 3/4.3.5 now retains the requirements for the auto-matic initiation instrumentation and its surveillance and only modifies the action requirements to those appropriate with the downgraded status of RCIC.

Similarly, the second topic was the potential for RCIC operation to overfill the, reactor vessel.

To address this, the marked up Technical Specification 3/4.3.5 now also retains the requirements for the RCIC high reactor water. level. trip instrumentation.

8512100099 851205 PDR ADOCfC 05000397 P

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G. Adensam Page Two December 5,

1985 TECH.

SPEC.

AMENDMENT TO REFLECT RCIC SYSTEM DOWNGRADE RESULTING FROM MODIFICATIONS TO ADS LOGIC The only change is to again modify the action requirements to those appropriate with the downgraded status of RCIC.

The other two parts of the RCIC instrumentation system addressed in 3/4.3.5, specifically the condensate storage tank low water level transfer and the manual initiation, remain removed from this Technical Specification as is appropriate for the RCIC downgrade.

With the upgrade of the ADS actuation logic, these functions are no longer required to demonstrate RCIC availability as a functioning backup to HPCS for design basis events.

Additionally, based on the limitations placed on minimum condensate storage tank levels and the high suppression pool level switchover logic built into the HPCS system

design, a minimum of 141 minutes is available to the operator to allow manual RCIC transfer to the suppression pool from the condensate storage tanks.

The safety significance of deleting manual RCIC initiation from this table also should not be an issue since, as discussed above, operation in either the automatic or manual mode is not required to mitigate design basis events.

Both the condensate storage tank low water level transfer and manual initia-tion functions will be tested in accordance with the balance of plant portion-of the plant maintenance and test procedures.

Additionally, the RCIC system will continue to utilize the condensate storage tanks as the preferred make-up water source for plant isolation events.

The last topic was the concern for maintaining RCIC pump discharge piping to the reactor vessel full of water to minimize the potential for water hammer effects.

The surveillance requirement for verifying high point venting and complete filling of the piping was removed when the entire RCIC system Technical Specification 3/4.7.3 was removed in the proposed amendment.

However, the quarterly ASME pump and valve surveillance testing which is still required by Technical Specification 4.0.5 incor-porates in its procedures a verification of full system discharge piping by high point venting.

It should also be noted that RCIC system discharge piping pressurization is monitored continuously and alarmed by an annunciator in the Control Room.

Thus, any time that the RCIC waterleg pump should fail, system injection line pressure will decrease and an alarm in the Control Room will alert the operators to a potential system fill deficiency.

This provides the operators with a warning that RCIC system fill status may be in jeopardy and requires a verification of system fill.

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G. Adensam Page Three December 5,

1985 TECH.

SPEC.

AMENDMENT TO REFLECT RCIC SYSTEM DOWNGRADE RESULTING FROM MODIFICATIONS TO ADS LOGIC Additionally, the remaining parts of the deleted surveillance section (4.7.3) for RCIC, specifically the valve lineup verification, flow controller and 18 month surveillance requirements will be retained and transferred to the balance of plant portion of the plant maintenance and test procedures.

Should you have any questions, please contact Mr. P. L. Powell, Manager, WNP-2 Licensing.

Very truly yours, G.

C. Sory sen, Manager Regulatory Programs HLA/tmh Attachments cc:

RC Barr - BPA JO Bradfute -

NRC C

Eschels EFSEC JB Martin -

NRC RV E

Revell - BPA NS Reynolds - BLCPSR AD Toth -

NRC Site

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