ML050530057

Proposed Technical Specifications Change Request Relocation of Inservice Inspection and Testing Requirements Replacement Pages

ML050530057
Person / Time
Site:	Surry
Issue date:	02/21/2005
From:	Hartz L Virginia Electric & Power Co (VEPCO)
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
04-666A
Download: ML050530057 (6)

Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 2326 1 February 21, 2005 U.S. Nuclear Regulatory Commission Serial No. 04-666A Attention: Document Control Desk NL&OS/ETS RO Washington, D.C. 20555 Docket Nos. 50-280, 281 License Nos. DPR-32, 37 Vl RGINIA ELECTRIC AND POWER COMPANY (DOMINION)

SURRY POWER STATION UNITS 1 AND 2 PROPOSED TECHNICAL SPECIFICATIONS CHANGE REQUEST RELOCATION OF INSERVICE INSPECTION AND TESTING REQUIREMENTS REPLACEMENT PAGES In a letter dated November 4, 2004 (Serial No.04-666), Dominion requested an amendment to Facility Operating License Numbers DPR-32 and DPR-37 in the form of changes to the Technical Specifications (TS) for Surry Power Station Units 1 and 2.

The proposed changes will relocate the inservice testing requirements, remove the inservice inspection requirements, and establish a Bases Control Program consistent with Improved Technical Specifications.

Subsequent to the submittal, it was identified that an incorrect TS section reference and minor typographical errors were included in page 4 of 8 of the Discussion of Change section in Attachment 1 to the letter. It was also noted that the proposed TS Section 6.4.1, Inservice Testing Program, on TS page 6.4-6 in Attachment 3 was not consistent with the changes specified in both the Discussion of Change (page 3 of 8, Attachment

1) and the marked-up TS pages (Insert A, Attachment 2). Therefore, please replace page 4 of 8 in Attachment 1 and proposed TS page 6.4-6 in Attachment 3 of our November 4, 2004 submittal with the corrected pages provided in the attachment to this letter. These changes are administrative in nature and therefore do not affect the No Significant Hazards Consideration Determination or the Environmental Assessment included in the original submittal.

If you have any questions or require additional information, please contact Mr. Thomas Shaub at (804) 273-2763.

Very truly yours, Leslie N. Hartz Vice President - Nuclear Engineering Attachment Commitments made in this letter: None

Serial No. 04-666A Docket Nos. 50-280/281 Page 2 of 3 cc: U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW Suite 23T85 Atlanta, Georgia 30303 Commissioner Bureau of Radiological Health 1500 East Main Street Suite 240 Richmond, Virginia 23218 Mr. N. P. Garrett NRC Senior Resident Inspector Surry Power Station Mr. S. R. Monarque NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 8-H12 Rockville, Maryland 20852

Serial No. 04-666A Docket Nos. 50-280/281 Page 3 of 3 Technical Specifications Change - IST, IS1 and Bases Control Program COMMONWEALTH OF VIRGINIA )

COUNTY OF HENRICO 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 this %aly of 2005.

My Commission Expires:

Notary Public (SEAL)

Attachment ReDlacement Paaes for Virainia Electric and Power ComDanv Letter to USNRC dated November 4.2004 (Serial No.04-666)

Page 4 of 8, Attachment 1, Discussion of Change Proposed TS Page TS 6.4-6, Attachment 3 Surry Power Station Units 1 and 2 Virginia Electric and Power Company (Dominion)

3. The provisions of TS 4.0.3 are applicable to inservice testing activities; and

4. Nothing in the ASME Code for Operation and Maintenance of Nuclear Power Plants shall be construed to supersede the requirements of any TS.

The frequencies identified in the table above are those identified in the ASME Code for Operation and Maintenance of Nuclear Power Plants.

The following TS are revised to refer to the Inservice Testing Program in place of TS 4.0.5:

J TS 4.1 .B.1 - Pressurizer PORVs and Block Valves J TS Table 4.1 -2A Item 4 - Pressurizer Safety Valves J TS Table 4.1 -2A Item 5 - Main Steam Safety Valves J TS 4.5.A.1 - Containment Spray Pumps J TS 4.5.A.2 - Containment Spray Valves J TS 4.5.B.1 - Recirculation Spray Pumps J TS 4.5.8.2 - Recirculation Spray Valves J TS 4.8.A.2.a - AFW Valves J TS 4.8.A.3.a - AFW Pumps J TS 4.8.A.5.b - AFW Cross Connect Valves J TS 4.1 1.C.1 - Safety Injection Subsystem Low Head Pumps J TS 4.1 1.C.2 - Safety Injection Subsystem Charging Pumps J TS 4.1 1.C.3 - Safety Injection Subsystem Valves The following TS are revised to eliminate reference to ASME Section XI. Section XI is no longer the appropriate ASME Code of reference for the Inservice Testing Program.

J TS 4.8.8 - Acceptance Criteria The following TS are revised due to the removal of the IS1 program requirements from the TS:

J TS 4.2.A - Augmented Inspections J TS Table 4.2-1 Item 2.1 .I both examination requirements and frequency Item 2.1.2 both examination requirements and frequency R Item 2.1.3 both examination requirements and frequency J TS 4.17 - Shock Suppressors (Snubbers)

Section XI continues to be referenced in TS 4.2 as it relates to the examination methods and frequency of the augmented inspections.

Page 4 of 8

TS 6.4-6 H. Practice of site evacuation exercises shall be conducted annually, following emergency procedures and including a check of communications with off-site report groups.

I. Inservice Testing Program This program provides controls for inservice testing of ASME Code Class 1,2, and 3 components. The program shall include the following:

1. Testing frequencies specified in the ASME Code for Operation and Maintenance of Nuclear Power Plants and applicable Addenda as follows:

ASME Code for Operation and Maintenance of Nuclear Power Plants and applicable Addenda Required Frequencies for terminology for inservice testing performing inservice testing activities activities Quarterly or every 3 months At least once per 92 days Yearly or annually At least once per 366 days Biennially or every 2 years At least once per 73 1 days Every 4 years At least once per 1461 days Every 5 years At least once per 1827 days Every 8 years At least once per 2922 days Every 10 years At least once per 3653 days Once per fuel cycle (18 months) At least once per 549 days Every cold shutdown Every cold shutdown Every refueling outage Every refueling outage

2. The provisions of TS 4.0.2 are applicable to the above required Frequencies for performing inservice testing activities;

3. The provisions of TS 4.0.3 are applicable to inservice testing activities; and

4. Nothing in the ASME Code for Operation and Maintenance of Nuclear Power Plants shall be construed to supersede the requirements of any TS.

J. Technical Specifications (TS) Bases Control Program This program provides a means for processing changes to the Bases of these Technical Specifications.

1. Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.

Amendment Nos.