ML20202B170
| ML20202B170 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 07/03/1986 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton, Rubenstein L Office of Nuclear Reactor Regulation |
| References | |
| 86-426, NUDOCS 8607100223 | |
| Download: ML20202B170 (3) | |
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I VINGINIA ELECTHIC AND POWEH COM1%NY HICHMOND, VI HO bilA 2 H 2 61 ,
W L. SrasWANT Va c a P"""' """'
Nt:ctsaa oPERATEONS July 3, 1986 e
Mr. Harold R. Denton, Director Serial No.86-426 Office of Nuclear Reactor Regulation N0/TAH/vlh .
Attn: Mr. Lester S. Rubenstein, Director Docket Nos. 50-338 PWR Project Directorate No. 2 50-339 Division of PWR Licensing-A License Nos. NPF-4 U.S. Nuclear Regulatory Commission NPF-7 Washington, D.C. 20555 Gentlemen':
! VIRGINIA ELECTRIC AND POWER COMPANY ,
L NORTH ANNA POWER STATION UNIT NOS. 1 AND 2 LICENSE AMENDMENT FOR CORE UPRATE By letter dated May 2,1985, Virgin ~ia Electric and' Power Company requested an amendment to the North Anna Unit 1 and 2 Technical Specifications to allow operat' ion with a nominal core thermal power rating of 2893 Mwt.
By letter dated October 23, 1985, the NRC Staff requested additional informatic n conce~rning the proposed core uprating. Our letter, dated February t;, 1986, provided the response to the request.
This response was based in part on the assumption that the North Anna Emergency Operating Procedures would be revised based on Revision 1 to the Westinghouse Owners Group Emergency Response Guidelines (Rev. 1 WOG/ ERGS) prior to the anticipated date of implementation of the core
- uprating. However, as a result of a recent audit by the NRC, of the North Anna Emergency Operating Procedure generation process, the implementation of the Rev.1 WOG/ ERG based procedures has been delayed from June 30, 1986
- until April 30, 1987. The purpose of this letter is to inform you that .
we have performed a review to insure the accuracy of our. responses to the October 23, 1985 request for additional information and to provide you with the results of the review.
The review was performed to identify any assumptions in our response which are inconsistent with operator actions directed by the current versus the revised Emergency Operating Procedures. Also, proposed corrections were to be provided- if any discrepancies were identified. The responses to questions 1.b and 2.c of the staff's request were determined to be dependent upon operator actions and therefore are potentially affected. s 8607100223 860703 ,
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w Viaolvd EtzrTRIC AND Powna COMPANY TO Mr. Harold R. Denton Th'e response to item 1.b concerned a locked rotor acci. dent with.a s. tuck #
open steam generator PORV. To assure consistency with our response, it ,
will be necessary to modify the existing ~ procedures by changing step 7 of EP-2 to verify isolation of (or manually cicse) the SG PORVs 'and the SG Blowdown in addition to isolating all feedwater, as the current procedure requires. -
-t' Item 2.c concerned small break LOCAs from 1000 psig without accumuytors.
Our response to this item remains viable with the existing procedures..
The Critical- Safety Function Status Trees for Core Cooling in both Rev.
1 WOG/ ERG based procedures and the existing procedures, monitor the Core
- Exit Thermocouples (CETs) and the Reactor Vessel Liquid Inventory. Systern (RVLIS). If the CETs exceed 700'F or if RVLIS indicates core uncovery, the procedures transitioned to, in both the current and the upgraded ,
versions ~ will iiirect the operator to depressurize the Reactor ' Coolant System via steam . generator secondary side depressurization. This is consistent with the February 6, 1986 response.
The conclusion from this review is that even though the responses to the NRC questions were written assuming that Rev. 1 WOG/ ERG based E0Ps would be implemented, they remain applicable for the current procedures during the interim period. However, the change described above will be made to' the existing procedures prior to implementation of the core uprating in order to insure consistency with our response of February 6,1986.
Very truly yours,
'\
pm W. L. Stewart e
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VamotxlA ELucinIC AND Powna COMPANY TO
-Mr. Harold R. Dento.n cc: Dr. J. Nelson Grace '
Regional Administrator NRC Region II Mr. J. L. Ca' 1dwell NRC Senior Resident Inspector North Anna Power Station - --
. . . .1-i Mr. Leon B. Engle NRC North Anna Project Manager , ,
PWR Project Directorate No. 2
- Division of PWR Licensing-A
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