ML20067C530
| ML20067C530 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 02/06/1991 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20067C532 | List: |
| References | |
| 91-013, 91-13, NUDOCS 9102120101 | |
| Download: ML20067C530 (3) | |
Text
._ _ _ _ _ _ _ _ _____
YlitolNI A U1.1T1111C ANI) I'OWI;H Cubil'ANY li triistok u, Viseuixir unu ta February 6,1991 United States Nuclear Regulatory Commission Serial No.
91 013 Attention: Documont Control Desk NO/ETS Washington, D. C. 20555 Docket No.
50 281 License No.
DPR 37 Gentlemen:
y_lRGINIA ELECTRIC AND POWER COMPANY ERRY POWER STATION UNIT 2 PROPOSED IECHNICAL SPECIFICATION FOR THE MAIN CONTROL ROOM AND EMERGENCY SWITCHGEAR RQQld AIR hat [DLING UNITS Pursuant to 10 CFR 50.90, the Virginia Electric and Power Company requests an amendment, in the form of a change to the Technical Specifications, for Surry Power Station Unit 2. As part of our effort to upgrade the Main Control Room (MCR) and Emergency Switchgear Room (ESGR) air conditioning system, the Unit 2 air handling units (AHU) are scheduled to be replaced during the upcoming refueling outage.
Installation of new Unit 2 air handling units will return the system to the original AHU design configuration. The proposed Technical Specification change eliminetec the present interim operating restrictions for the Unit 2 ESGR air handling units and provides technical specifications consistent with the permanent AHU design configuration. This change is consistent with our previous Technical Specification change request for Unit 1, dated June 26,1990 (Serial No. 90 271) and the corresponding previous Technical Specification amendment No.145, issued October 11, 1990. The proposed change for Unit 2 is included in Attachment 1.
We are requesting that the Technical Specification become effective when the IJnit 2 AHUs are Installed and operational at the end of the Unit 2 refueling outage.
In addition, preparatcry work to support the installation of additional chiller capacity will also be performed during the Unit 2 refueling outage. Installation of the additional safety related chiller capacity will occur as non outage work following Unit 2 refueling.
The schedule for installation of this additional chiller capacity has not yet been finalized, although it is our intention to initiate this activity late in 1991 or early 1992.
()0 I l 0102120101 910206 PDR ADOCK 05000281 P
I This request has been reviewed and approved by tne Station Nuclear Safety and Operating Committee and the Management Safety Review Committee. It has been determined that the proposed changes do not involve an unreviewed safety question as defined in 10 CFR 50.59 or a significant hazards consideration as defined in 10 CFR 50.92. The basis for our no significant hazards consideration determination is included in Attachment 2.
Very truly yours, b
h-L b ( m ~3_
W. L. Stewart Senior Vice President Nuclear Attachments cc-U. S. Nuclear Regulatory Commission Region 11 101 Marietta Street, N. W.
Suite 2000
' Atlanta, Georgia 30323 Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station Commissioner Department of Health Room 400 109 Governor Street Richmond, Virginia 23219
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i COMMONWEALTH OF VIRGINIA )
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COUNTYOF HENRICO
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The foregoing document was acknowled0ed before me, in and for the County and Commonwealth aforesaid, today by W. L. Stewart who is Senior Vice President Nuclear, of Virginia Electric and Power Company.
He is duly authorized to execute and file the foregoing document in behalf of i
that Company, and the statemei s in the document are true to the best of his knowledge and belief.
Acknowledged before me this d
day of
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My Commission Expires:
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