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| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE | | document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE | ||
| page count = 4 | | page count = 4 | ||
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{{#Wiki_filter:.. e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 December 10, 1993 United States Nuclear Regulatory Commission Attention: | {{#Wiki_filter:.. | ||
Document Control Desk Washington, D. C. 20555 Gentlemen: | e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 December 10, 1993 United States Nuclear Regulatory Commission Serial No. 93-401A Attention: Document Control Desk NL&P/ETS Washington, D. C. 20555 Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 Gentlemen: | ||
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 PROPOSED TECHNICAL SPECIFICATION CHANGES AUGMENTED INSPECTION PROGRAM SENSITIZED STAINLESS STEEL | VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 PROPOSED TECHNICAL SPECIFICATION CHANGES AUGMENTED INSPECTION PROGRAM SENSITIZED STAINLESS STEEL On July 2, 1993, Virginia Electric and Power Company requested changes to the Technical Specifications for Operating License Nos. DPR-32 and DPR-37, Surry Power Station Units 1 and 2, respectively. The proposed changes updated the augmented inspection program for sensitized stainless steel by incorporating the newer Code requirements, while maintaining the augmented inspection philosophy of the Atomic Safety and Licensing Board (ASLB). In a December 1, 1993 telephone conference call, the staff requested specific clarification of the "at three times the frequency" inspection criterion for sensitized stainless piping included in our Augmented Inspection Program. It remains our intent to conduct examination of the sensitized stainless steel piping included in Technical Specification Table 4.2-1, Items 2.1.1 and 2.1.2, at three times the frequency of the Code. This clarification has been incorporated into the Basis of Technical Specification 4.2 and the 1O year interval requirements of Table 4.2-1 for Items 2.1.1 and 2.1.2. The revised pages are included in Attachment 1. | ||
The proposed changes updated the augmented inspection program for sensitized stainless steel by incorporating the newer Code requirements, while maintaining the augmented inspection philosophy of the Atomic Safety and Licensing Board (ASLB). In a December 1, 1993 telephone conference call, the staff requested specific clarification of the "at three times the frequency" inspection criterion for sensitized stainless piping included in our Augmented Inspection Program. It remains our intent to conduct examination of the sensitized stainless steel piping included in Technical Specification Table 4.2-1, Items 2.1.1 and 2.1.2, at three times the frequency of the Code. This clarification has been incorporated into the Basis of Technical Specification 4.2 and the | As discussed during the December 1, 1993 telephone conference call, this Cost Beneficial Licensing Action submittal was proposed to reduce requirements which are marginal to safety by using the current Code examination requirements in fulfilling the ASLB augmented inspection requirements. The sensitized stainless steel piping in both units has been examined at three times the frequency for approximately 20 years without any indications which were attributed to sensitization. | ||
The proposed clarification has been reviewed and approved by the Station Nuclear Safety and Operating Committee and the Management Safety Review Committee. The proposed clarification is editorial in nature and does not alter the intent of the original submittal. Therefore, the clarification does not involve an unreviewed safety question as | |||
The sensitized stainless steel piping in both units has been examined at three times the frequency for approximately 20 years without any indications which were attributed to sensitization. | /JODI I (I | ||
The proposed clarification has been reviewed and approved by the Station Nuclear Safety and Operating Committee and the Management Safety Review Committee. | |||
The proposed clarification is editorial in nature and does not alter the intent of the original submittal. | defined in 10 CFR 50.59 or create a significant hazards consideration as defined in 1o CFR 50.92. The significant hazards consideration determination submitted on July 2, 1993 remains bounding. | ||
Therefore, the clarification does not involve an unreviewed safety question as /JODI I ( I defined in | If you have any questions or require additional information, please contact us. | ||
If you have any questions or require additional information, please contact us. Very truly yours, QP~ 'fvvW. L. Stewart Senior Vice President | Very truly yours, QP~ | ||
-Nuclear Attachment | 'fvvW. L. Stewart Senior Vice President - Nuclear Attachment | ||
: 1. Revised Technical Specifications cc: U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W. Suite 2900 Atlanta, Georgia 30323 Mr. M. W. Branch NRC Senior Resident Inspector Surry Power Station Commissioner Department of Health Room 400 109 Governor Street Richmond, Virginia 23219 | : 1. Revised Technical Specifications cc: U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W. | ||
-Nuclear Operations, for W. L. Stewart who is Senior Vice President | Suite 2900 Atlanta, Georgia 30323 Mr. M. W. Branch NRC Senior Resident Inspector Surry Power Station Commissioner Department of Health Room 400 109 Governor Street Richmond, Virginia 23219 | ||
-Nuclear, of Virginia Electric and Power Company. He is duly authorized to execute and file the foregoing document in behalf of that Company, and the statements in the document are true to the best of his knowledge and belief. Acknowledged before me this )07l'day of i(1C-fltobN , 1s1:s_. My Commission Expires: l,. }Y) 31 , 19:1..!/:.. | |||
~~*+/-hrlL | COMMONWEALTH OF VIRGINIA ) | ||
) | |||
COUNTY OF HENRICO ) | |||
The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by J. P. O'Hanlon, who is Vice President - Nuclear Operations, for 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 that Company, and the statements in the document are true to the best of his knowledge and belief. | |||
Acknowledged before me this )07l'day of i(1C-fltobN , 1s1:s_. | |||
My Commission Expires: l,. }Y) ~ 31 , 19:1..!/:.. | |||
~~*+/-hrlL NotaryPblic (SEAL)- | |||
e Attachment 1 Surry Power Station Proposed Supplemental Technical Specification Changes}} | |||
Latest revision as of 22:02, 2 February 2020
| ML18153B403 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 12/10/1993 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML18153B404 | List: |
| References | |
| 93-401A, NUDOCS 9312200165 | |
| Download: ML18153B403 (4) | |
Text
..
e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 December 10, 1993 United States Nuclear Regulatory Commission Serial No. 93-401A Attention: Document Control Desk NL&P/ETS Washington, D. C. 20555 Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 PROPOSED TECHNICAL SPECIFICATION CHANGES AUGMENTED INSPECTION PROGRAM SENSITIZED STAINLESS STEEL On July 2, 1993, Virginia Electric and Power Company requested changes to the Technical Specifications for Operating License Nos. DPR-32 and DPR-37, Surry Power Station Units 1 and 2, respectively. The proposed changes updated the augmented inspection program for sensitized stainless steel by incorporating the newer Code requirements, while maintaining the augmented inspection philosophy of the Atomic Safety and Licensing Board (ASLB). In a December 1, 1993 telephone conference call, the staff requested specific clarification of the "at three times the frequency" inspection criterion for sensitized stainless piping included in our Augmented Inspection Program. It remains our intent to conduct examination of the sensitized stainless steel piping included in Technical Specification Table 4.2-1, Items 2.1.1 and 2.1.2, at three times the frequency of the Code. This clarification has been incorporated into the Basis of Technical Specification 4.2 and the 1O year interval requirements of Table 4.2-1 for Items 2.1.1 and 2.1.2. The revised pages are included in Attachment 1.
As discussed during the December 1, 1993 telephone conference call, this Cost Beneficial Licensing Action submittal was proposed to reduce requirements which are marginal to safety by using the current Code examination requirements in fulfilling the ASLB augmented inspection requirements. The sensitized stainless steel piping in both units has been examined at three times the frequency for approximately 20 years without any indications which were attributed to sensitization.
The proposed clarification has been reviewed and approved by the Station Nuclear Safety and Operating Committee and the Management Safety Review Committee. The proposed clarification is editorial in nature and does not alter the intent of the original submittal. Therefore, the clarification does not involve an unreviewed safety question as
/JODI I (I
defined in 10 CFR 50.59 or create a significant hazards consideration as defined in 1o CFR 50.92. The significant hazards consideration determination submitted on July 2, 1993 remains bounding.
If you have any questions or require additional information, please contact us.
Very truly yours, QP~
'fvvW. L. Stewart Senior Vice President - Nuclear Attachment
- 1. Revised Technical Specifications cc: U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.
Suite 2900 Atlanta, Georgia 30323 Mr. M. W. Branch NRC Senior Resident Inspector Surry Power Station Commissioner Department of Health Room 400 109 Governor Street Richmond, Virginia 23219
COMMONWEALTH OF VIRGINIA )
)
COUNTY OF HENRICO )
The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by J. P. O'Hanlon, who is Vice President - Nuclear Operations, for 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 that Company, and the statements in the document are true to the best of his knowledge and belief.
Acknowledged before me this )07l'day of i(1C-fltobN , 1s1:s_.
My Commission Expires: l,. }Y) ~ 31 , 19:1..!/:..
~~*+/-hrlL NotaryPblic (SEAL)-
e Attachment 1 Surry Power Station Proposed Supplemental Technical Specification Changes