ML060540421

Proposed Technical Specification Change and Supporting Safety Analyses Revisions to Address Generic Safety Issue 191 Revised Marked-Up Technical Specifications Pages

ML060540421
Person / Time
Site:	Surry
Issue date:	02/23/2006
From:	Hartz L Virginia Electric & Power Co (VEPCO)
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
06-014A, GSI-191
Download: ML060540421 (6)

Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA23261 February 23, 2006 U. S. Nuclear Regulatory Commission Serial No. 06-0 14A Attention: Document Control Desk NL&OS/PRW RO One White Flint North Docket Nos. 50-280/281 11555 Rockville Pike License Nos. DPR-32/37 Rockville, MD 20852-2738 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 PROPOSED TECHNICAL SPECIFICATION CHANGE AND SUPPORTING SAFETY ANALYSES REVISIONS TO ADDRESS GENERIC SAFETY ISSUE 191 REVISED MARKED-UP TECHNICAL SPECIFICATIONS PAGES In a letter dated January 31, 2006 (Serial No.06-014), Virginia Electric and Power Company (Dominion) submitted a Technical Specifications (TS) change request for Surry Power Station Units 1 and 2. The proposed change was submitted as part of Dominions resolution to NRC Generic Safety Issue 191. In Attachment 2 to that letter, Dominion provided marked-up TS pages that included the requested changes.

Subsequent to the submittal of the proposed TS change, it was discovered that two of the marked-up TS pages contained administrative errors. Specifically, TS Table 3.7-6, Item 9a, should have been marked-up to note the change of the Functional Unit description from RWST Level-Low to RWST Level-Low-Low. In addition, the phrase from 70°F to 95°F service water temperatures in the last paragraph on TS page TS 3.8-4 was incorrectly inserted between the words sloped line. The phrase should have been inserted after these words instead. Therefore, please replace the marked-up TS pages TS 3.7-26 and TS 3.8-4 included in Attachment 2 of our previous submittal with the corrected marked-up TS pages provided in the attachment to this letter. The discussion of the TS changes and the typed proposed TS pages included in Attachments 1 and 3 of the previous submittal, respectively, are correct and therefore do not require revision.

If you have any questions regarding this submittal, please contact Mr. Paul R.

Willoughby at (804) 273-3572.

Very truly yours, Leslie N. Hartz d Vice President - Nuclear Engineering Attach ment

Serial No. 06-014A Docket Nos. 50-2801281 Page 2 of 3 cc: U. S. Nuclear Regulatory Commission Regional Administrator - Region II Sam Nunn Atlanta Federal Center Suite 23 T85 61 Forsyth Street, SW Atlanta, Georgia 30303-8931 Mr. S. R. Monarque Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 8 H 12 11555 Rockville Pike Rockville, MD 20852-2738 Mr. N. P. Garrett Senior Resident Inspector Surry Power Station Commissioner Bureau of Radiological Health 1500 East Main Street Suite 240 Richmond, VA 23218

Serial No. 06-014A Docket Nos. 50-280/281 Page 3 of 3 COMMONWEALTH OF VIRGINIA 1 1

COUNTY OF HENRICO 1 The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by Leslie N. Hartz, who is Vice President - Nuclear Engineering, of Virginia Electric and Power Company. She has affirmed before me that she is duly authorized to execute and file the foregoing document in behalf of that Company, and that the statements in the document are true to the best of her knowledge and belief.

Acknowledged before me the ~?3? day of \"%ha &?&4 ,2006.

My Commission Expires: 3/. daO6 Notary Public (SEAL)

Serial No.06-014A Docket Nos. 50-280/281 ATTACHMENT CORRECTED MARKED-UP TECHNICAL SPECIFICATIONS PAGES TS3.7-26AND TS 3.8-4 Virginia Electric and Power Company (Dominion)

Surry Power Station Units 1 and 2

TABLE 3.7-4 ENGINEERED SAFETY FEATURE SYSTEM INITIATION LIMITS INSTRUMENT SE'ITING HQb 6 AUXILIARY FEEDWATER

a. Steam Generator Water Level Low-Low Aux. Feedwater Initiation 2 14.5% narrow range S/G Blowdown Isolation

b. RCP Undervoltage Aux. Feedwater Initiation 2 70% nominal

c. Safety Injection Aux. Feedwater Initiation All S.I. setpoints

d. Station Blackout Aux. Feedwater Initiation 2 46.7% nominal

e. Main Feedwater Pump Trip Aux. Feedwater Initiation N.A.

7 LOSSOFPOWER

a. 4.16 KV Emergency Bus Undervoltage Emergency Bus Separation 2 2975 volts and I 3 2 6 5 volts (Loss of Voltage) and Diesel start with a 2 (+5, -0.1) second time delay

b. 4.16 KV Emergency Bus Undervoltage Emergency Bus Separation 2 3830 volts and I 3 8 8 1 volts (Degraded Voltage) and Diesel start with a 60 (f3.0) second time delay (Non CLS, Non SI) 7 (f0.35) second time delay (CLS or SI Conditions) 8 NON-ESSENTIAL SERVICE WATER ISOLATION 8E.

(I, a. Low Intake Canal Level Isolation of Service Water flow to non-essential loads 23 feet-6 inches 9 RECIRCULATION MODE TRANSFER 2r

a. RWST L e v e l - L o m Initiation of Recirculation 2 11.25%

0 Z

Mode Transfer System 515.75% I 10 TURBINE TRIP AND FEEDWATER ISOLATION

a. Steam Generator Water Level High-High Turbine Trip 5 80% narrow range Feedwater Isolation

TS 3.8-4 88-83.45-(3) assuring that environmental conditions will not preclude access to close the valves and

4) that this administrative or manual action will prevent the release of radioactivity outside the containment.

The Reactor Coolant System temperature and pressure being below 350°F and 450 psig, respectively, ensures that no significant amount of flashing steam will be formed and hence that there would be no significant pressure buildup in the containment if there is a loss-of-coolant accident. Therefore, the containment internal pressure is not required to be subatmospheric prior to exceeding 350°F and 450 psig.

The allowable value for the containment air partial pressure is presented in TS Figure 3.8-1 for service water temperatures from 25 to 95°F. The RWST water shall {

have a maxhnmmperal Amendment Nos. 203-mM&