ML18152B385

Forwards Revised TS Basis Pages for TS 3.1.B,deleting Reactor Vessel Toughness Data Duplicated in Ufsar.Ref to Applicable UFSAR Section Included in TS Basis

ML18152B385
Person / Time
Site:	Surry
Issue date:	08/23/1999
From:	Christian D VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18152B360	List: ML18152B359 ML18152B385
References
99-404, NUDOCS 9908270141
Download: ML18152B385 (7)

Text

i .~ e VIRGINIA ELECTRIC AND PowER CoMPANY RICHMOND, VIRGINIA 23261 U.S. Nuclear Regulatory Commission Attention:

Document Control Desk Washington, D.C. 20555 Gentlemen:

August 23, 1999 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 TECHNICAL SPECIFICATIONS BASIS CHANGE Serial No.99-404 SPS-LIC/CGL, KL T RO Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 DELETE TABLES FOR REACTOR VESSEL TOUGHNESS DATA Virginia Electric and Power Company has approved a revision to the Basis for Technical Specification (TS) 3.1.B, "Heatup and Cooldown".

This change deletes reactor vessel toughness data that is duplicated in the UFSAR. In addition to deletion of the redundant information, a reference to the applicable UFSAR section is included in the TS Basis. The TS Basis revision is provided for your information.

A UFSAR change associated with this TS Basis revision is currently being processed and will be included in the next scheduled UFSAR update. The UFSAR change updates the reactor vessel toughness data consistent with information previously provided to the NRC in a February 24, 1999 letter (Serial No.99-034). The TS Basis revision has been reviewed and appmved by the Station Nuclear Safety and Operating Committee and the ManagemenCSafety Review Committee.

It has been determined that this change does not involve an unreviewed safety question as defined in 10 CFR 50.59. A discussion of the TS Basis change, the mark-up of the TS Basis change, and the revised TS Basis are provided in Attachments 1, 2, and 3, respectively.

Should you have any questions or require additional information, please contact us. Very truly yours, David A. Christian Vice President

-Nuclear Operations e Attachments:

1 . , Discl!ssion of Change 2. Mark-up of Technical Specification Basis 3. Revised Technical Specification Basis Commitments made in this letter: 1. A UFSAR change associated with the revised reactor vessel toughness data provided to the NRC in response to Generic Letter 92-01, Supplement 1, Revision 1, is currently being processed, and will be included in the next scheduled UFSAR update. cc: U.S. Nuclear Regulatory Commission Region II Atlanta Federal Center 61 Forsyth Street, SW Suite 23T85 Atlanta, Georgia 30303 Mr. R. A. Musser NRC Senior Resident Inspector Surry Power Station Commissioner

-Department of Radiological Health Room 104A 1500 East Main Street Richmond, VA 23219

= **, -~.' ' , -. COMMONWEAL TH OF VIRGINIA ) ) COUNTY OF HENRICO ) The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by David A. Christian, who is Vice President

-Nuclear Operations, of Virginia Electric and Power Company. He has affirmed before me that he is duly authorized to execute a_nd file the foregoing document in behalf of that Company, and that the statements in the document are true to the best of his knowledge and belief. -.:: -* Acknowledged before me this AJt4iay of ¥ , 19 CJC/. My Commission Expires: j} 31 J ;2 {1)(0 . otary Public (SEAL/

ATTACHMENT 1 DISCUSSION OF CHANGE VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 e DISCUSSION OF CHANGE INTRODUCTION Virginia Electric and Power Company (Virginia Power) is revising the Surry Technical Specification (TS) 3.1.B Basis to delete Tables 3.1-1 and 3.1-2 and instead reference identical information that is contained in the Surry Updated Final Safety Analysis Report (UFSAR). The revised TS Basis is necessary to prevent potential consistency concerns between the Surry Technical Specifications and the UFSAR. BACKGROUND TS 3.1.B Basis Tables 3.1-1 and 3.1-2 of the Surry Technical Specifications currently contain information regarding Reactor Vessel Toughness Data that is identical to the information included in Surry UFSAR Tables 4.1-14 and 4.1-15. The data in these tables require update to reflecMhe latest information that was submitted to the NRC in a letter dated February 24, 1999. Because the information is identical in both documents, and because it is referenced only by the Basis for Technical Specification (TS) 3.1.B, the Basis requires revision to delete the two tables and instead reference the updated tables in the UFSAR. Licensing/Design Basis The Virginia Power response to Generic Letter 92-01, Revision 1, is documented in BAW-2222, "Reactor Vessel Working Group Response to Closure Letters to NRC Generic Letter 92-01, Revision 1," dated June 1994. A resultant TS change request was submitted to the NRC in a letter dated June 8, 1995 (Serial No.95-197) that included modifications to TS Tables 3.1-1 and 3.1-2 and was approved by the NRC in a letter dated December 28, 1995 (TS Amendments 207). Since the publication of BAW-2222 in June 1994, Framatome Technologies has published BAW-2313, Revision 1, "B&WOG Reactor Vessel Working Group Reactor Vessel Materials and Surveillance Data Information, Volumes 1 and 2," dated December, 1998. After an evaluation of data contained in BAW-2313, Revision 1, Virginia Power submitted a supplemental letter to the NRC dated February 24, 1999, to incorporate the most recent : reactor vessel materials information into our docketed response to Generic Letter 92-01, Revision 1, Supplement

1. This submittal included more recent values of "mean for the heat" chemical composition for Surry Units 1 and 2 reactor vessel beltline materials, which will be reflected-in-UFSAR Table 4.1-14 and Table 4.1-15. Therefore, deletion of Tables 3.1-1 and 3.1-2 from the TS 3.1.B Basis will eliminate inconsistencies between the two documents and simplify any future revisions to the data. Page 1 of 3 SPECIFIC CHANGES As noted above, the revised TS Basis for TS 3.1.B deletes two tables that are redundant to existing UFSAR tables. The specific revisions are as follows: In the Basis of TS 3.1.B, under item 6), reference to Tables 3.1-1 and 3.1-2 is changed to, "UFSAR Section 4.1." -At the end of the Basis for TS 3.1.B, a reference table is added to reflect UFSAR Section 4.1. -TS Basis 3.1 Tables 3.1-1 and 3.1-2 are deleted. SAFETY SIGNIFICANCE The revision to the Surry Technical Specification 3.1.B Basis deletes two tables that are redundant to existing UFSAR tables. Reference to the TS Basis tables that are being deleted is changed to reference the UFSAR instead. Deletion of the redundant information eliminates the possibility that the two sets of information could be updated inconsistently.

The information will continue to be controlled and maintained up to date in the UFSAR, and any future changes to the UFSAR tables will be reviewed in accordance with the requirements of 10 CFR 50.59. Consequently, no change to the licensing basis results from this revision.

There is no safety significance associated with this revised TS Basis, since it does not involve any plant modifications or changes in system operation, is consistent with the Surry licensing and design bases, and does not affect the existing accident analyses, which remain bounding.

Furthermore, no chang.e to the TS limiting conditions for operation is required.

Page 2 of 3 REF.ERENCES

1. BAW-2222, "Reactor Vessel Working Group Response to Closure Letters to NRC Generic Letter 92-01, Revision 1," dated June 1994. 2. Letter from J. P. O'Hanlon to USNRC, "Virginia Electric and Power Company, Surry Power Station Units 1 and 2, Request for Exemption

-ASME Code Case N-514, Proposed Technical Specifications Change, Revised Pressure/Temperature Limits and L TOPS Setpoint," dated June 8, 1995 (Serial No.95-197). 3. Letter from B. C. Buckley (USNRC) to J. P. O'Hanlon, "Surry Units 1 and 2 -Issuance of Amendments Re: Surry Units 1 and 2 Reactor Vessel Heatup and Cooldown Curves," dated December 28, 1995 (Serial No.96-020). 4. BAW-2313, Revision 1, "B&WOG Reactor Vessel Working Group Reactor Vessel Materials and Surveillance Data Information, Volumes 1 and 2," dated December 1998. 5. Letter from L. N. Hartz to USNRC, "Virginia Electric and Power Company, Surry . Power Station Units 1 and 2, Supplement to Virginia Power Response to NRC Request for Additional Information (RAI) on Generic Letter 92-01 Revision 1, Supplement 1," dated February 24, 1999 (Serial No.99-034). Page 3 of 3