ML18152A567
| ML18152A567 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna, 05000000 |
| Issue date: | 06/29/1984 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton, Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-1.C.1, TASK-TM 095A, 95A, NUDOCS 8407060175 | |
| Download: ML18152A567 (5) | |
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e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261
- w. L. STEWABT VtCB PRESIDBNT NucLBAll OPB:BATIONS June 29, 1984 Mr. Harold R. Denton, Director Office.of Nuclear Reactor Regulation Attn:
Mr. D. G. Eisenhut, Director Serial No. 095A NO/SRB/TAH:acm Docket Nos. 50-280 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D. C. 20555 50-281 50-338 50-339 Gentlemen:
License Nos. DPR-32 DPR-37 NPF-4 NPF-7' VIRGINIA ELECTRIC AND POWER COMPANY SURRY.POWER STATION NORTH ANNA POWER STATION RESPONSE TO PROCEDURE GENERATION PACKAGE ISSUES In response to Items 1 and 2 listed in your January 5, 1984 letter regarding the Procedure Generation Package (PGP) for Surry and North Anna, the following information is provided:
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The analysis for the Westinghouse Owners Group (WOG) generic Emergency Response Guidelines (ERG' s) has been performed for two broad categories of Westinghouse plants; those designed using Low Pressure (LP) s'afety Injection (SI) and those designed using a High Pressure (HP) SI system.
Surry Units #1 and #2 and North Anna Units #1 and #2 fall into the HP category and are therefore enveloped by the analysis performed for the HP plants.
The analysis was performed pursuant to NUREG 07 3 7, Item I. C. 1.
At the specific operator task leve'i a detailed review of each high level step will be performed during the Revision I upgrade from generic ERG's to plant specific procedures.
An example of the Surry Emergency Response Tracking Document form used to accomplish. this. review is provided as Attachment
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This form is intended to provide cross-reference capabilities between plant specific procedure steps and the ERG steps from which they are derived.
As appropriate, entries will provide information in the following areas:
Identified deviations of deletions/additions or sequencing are justified.
Plant* specific setpoints, as appropriate, are coded and cross-referenced to the Emergency
Response
Setpoint Document form (Attachment 2) which details derivation/justification for other than generic setpoints.
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PDR ADOCK 0500028 F
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e VIROINIA ELECTRIC AND POWER COMPANY TO Harold R. Denton Significant deviations to step content, other than minor wording, are identified and justified.
Applicable references are provided.
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Comparison of Surry and North Anna to the Generic Reference Plant has indicated a requirement for deviations between plant specif*ic procedures and generic guidelines due to certain *system component/functional differences.
These differences have been internally reviewed for safety significance with respect to the mitigating actions contained in our Emergency Response Procedure (ERP) set. As a result of this review there are no high level strategic deviations in their mitigating actions (as defined by Mr. H, B, Clayton at the NRC/WOG meeting of March 29, 1984).
The review has, however, identified tactical deviations largely due to system/component differences.
These are described below:
Residual Heat Removal (RHR)/Low Head SI system function dictates that long term core cooling requirements be addressed by use of the Low Head SI system v:ia the Recirculation Spray (RS) System and the RS sump.
Post accident containment cooling/depres~urization methods require step modifications to account for system component and :functional differences (e.g.
Surry and North Anna use containment and recirculation spray instead of fan coolers, etc.).
The safety injection system does not utilize separate high head safety injection pumps as described in the generic reference plant.
A recent modification to the Surry Boron Injection Tanks (BIT's) has
- removed concentrated boric acid from the BIT's.
3 *.
Response to Item 3 of the January 25, 1984 letter and concern. for instrumentation/control needs expressed in the March 29, 1984 NRC/WOG meeting and the H. B. Clayton/D. L. Zieman memorandum of April 5, 1984 summarizing that meeting is as follows:
Instrumentation and control requirements are identified in the ERG Revision 1 background documents.
Deviations, if any, and justifica-tion will be identified and documented prior to Revision 1 implementa-tion.
The Control Room Design Review Program Plan specifically addresses task analysis and adequacy of.the instrumentation and controls required to meet_ the identified needs.
To ensure consistancy and completeness, the Revision 1 development to Surry and North Anna ERP sets will coincide with and be inte-grated into the CRDR effort.
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e V1ao1NIA ELECT:a1c AND PowER CoMPANY To Harold R. Denton If there are further questions please contact us.
v7itrfl;f' W. L. *Stewart j:-
Enclosed:
ATTACHMENT 1 SURRY EMERGENCY RESPONSE TRACKING DOCUMENT ATTACHMENT 2 SURRY EMERGENCY RESPONSE SETPOINT DOCUMENT cc:
Mr. James P. O'Reilly Regional Administrator Region II USNRC Suite 2900 101 Marietta Street Atlanta, Georgia 30303 Mr. Steven A. Varga, Chief Operating Reactors Branch No. 1 Division of Licensing Mr. James R. Miller, Chief Operating Reactors Branch No. 3 Division of Licensing Mr. D. J. Burke NRC Resident Inspector Surry Power Station Mr. M. W. Branch NRC Resident Inspector North Anna Power Station
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SURRY POWER STATION EMERGENCY RESPONSE TRACKING DOCUMENT
===============================================================
SPS procedure designator=-----------------~
~OG guideline designator=-------------~---~
Rev. ____ _
Rev. ____ _
Procedure step=---------------------------------
Guideline step_=-------------------------------
CRITERIA COMMENTS
===============================================================
a>
Sequence Justification:
Guideline sequence YES_ ND_
===============================================================
b)
Set point Justification:
Setpoint required YES_ NO_-_
*==============================================================
c>
Significant deviation:
Significant Deviation YES_ NO_
===*==========================================================*
d)
References:
Guideline & *Background YES~ NO __
=============-=================================================
e>
Miscellaneous:
===========================================-===================
e Designation Number=------~-
SURRY POWER STATION EMERGENCY RESPONSE SETPOINT DOCUMENT
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Guideline/ Procedure Requirements=---------------------
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Requirement-Plant Speci fie=-----------------------
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Value Determination=-------------------------~--
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Justification=--------------------~---~----~
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Comments: _______________________________
~
Evaluator=--------------------~
Reviewer=---------------------~
Date: ______ _
Date: ______ _