ML20139A322

Provides Addl Info Re Generic Ltr 85-12,Items A.1 & C.2 on Implementation of TMI Action Item II.K.3.5, Automatic Trip of Reactor Coolant Pumps. Item 1.A,Part C Revised & Info Added to Item C.2 as Noted

ML20139A322
Person / Time
Site:	Beaver Valley
Issue date:	03/10/1986
From:	Carey J DUQUESNE LIGHT CO.
To:	Thompson H Office of Nuclear Reactor Regulation
References
TASK-2.K.3.05, TASK-TM 2NRC-6-020, 2NRC-6-20, GL-85-12, TAC-62926, NUDOCS 8603130293
Download: ML20139A322 (2)

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March 10, 19H6 UE,$*a"O*l'is*/$3 United States Nuclear Regulatory Commission Washington, DC 20555 ATTENTION:

Mr. Hugh L. Thompson, Jr., Director Division of Licensing Office of Nuclear Reactor Regulation

SUBJECT:

Beaver Valley Power Station - Unit No. 2 Docket No. 50-412 Revised Response to Generic Letter 85-12 "Implementat ion of TM1 Action Iten K.35,

' Automatic Trip of Reactor Coolant Pumps,' Schedule" REFERENCES : 1) NRC-5-124, dated August 27, 1985

2) 2NRC-5-146, dated November 15, 1985 Gentl emen:

The following change and additional in f ormat ion is being submitted for Beaver Valley Power Station Unit 2 (BVPS-2) in regards to Generic Letter 85-12 Items A.1 and C.2.

In I t em A.1 under "The Instrumentation Used to Determine when RCP Trip is Initiated is:" Part C should read as follows:

C) RCS pressure Indication (2RCS*P440 and 441_) Control Room Vertical Board - A (VB-A)

The underlines indicate the changes from BV S-2's previous submittal (2NRC 146, dated 11/15/85).

In item C.2, the following information relating to E0Ps which have RCP trip related operations is to be added:

A)

E-0 Series Symptomatic Response / Unexpected Conditions (ERGS fold-out) page:

The list of E0Ps below are Optimal Decovery Procedures which start and stop RCPs but do not use the 145 PSID criteria (i.e., no seal injection or leakoff, etc.).

• ES-0.1

" Reactor Trip Response"

• ES-0.2

" Natural Circulation Cooldown"

• ES -0.1

" Natural Circul at ion Cooldown with 5 team Void in Vessel (with RVLIS)"

• ES-0.4

" Natural Circulation Cooldown with Stern vold in Vessel (without RVLIS)"

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t United States Nuclear Regulatory Comission i

Mr. Hugh L. Thanpson, Jr., Director i

Revised Response to Generic Letter 85-12 i

Page 2 l

• ES-3.1

" Post-SGTR Cooldown using Backfill"

• ES-3.2

" Post-SGTR Cooldown using Blowdown"

• ECA-1,1 " Loss of Emergency Coolant Recirculation"

• ECA-2.1

" Uncontrolled Deprussurization of all Stean l

Generators"

• ECA-3.1 "SGTR with Loss of Reactor Cool ant--Subcooled Recovery Desired"

• ECA-3.2 "SGTR with Loss of Reactor Cool ant--Satur ated Recovery Desired"

• ECA-3.3 "SGTR without Pressurization Pressure Control" l

In add i t ion, under "C.

Function Restoration Procedur e s,"

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following two procedures are to be added.

Again, these procedures stop RO's i

based on other criteria than the 145 PSID criteria,

• FR-C.2

" Response to Degraded Core Cooling"

• FR-1.3

" Response to Voids in Reactor Vessel" Tne above infonnation conpletes BVPS-2's response to Generic Letter 85-12 addressing Section IV Implanentation Section of the SER enclosed, if there are any questions concerning this letter, please contact Mr. S. D. Hall of my staff.at (412) 643-5200.

DUQUESNE LIGHT MPANY

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. 'th r~iy Vice President 50H/wjs cc:

Mr. P. Taa, Project Manager Mr. W. Troskoski, Sr. Resident Inspector i

Mr. G. Walton, NRC Resident inspector INPO Records Center i

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