ML18153B004: Difference between revisions

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| document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS
| document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS
| page count = 6
| page count = 6
| project =
| stage = Request
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cc: U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, N.W.
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
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 }
 
COMMONWEALTH OF VIRGINIA }
                                     }
                                     }
COUNTY OF HENRICO                  )
COUNTY OF HENRICO                  )

Latest revision as of 23:09, 2 February 2020

Application for Amends to Licenses DPR-32 & DPR-37, Requesting Amendments in Form of Changes to TS to Eliminate Remaining References to cycle-specific Parameters in Surry TS
ML18153B004
Person / Time
Site: Surry  Dominion icon.png
Issue date: 07/14/1994
From: Ohanlon J
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18153B005 List:
References
94-413, NUDOCS 9407190369
Download: ML18153B004 (6)


Text

e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 July 14, 1994 U.S. Nuclear Regulatory Commission Serial No.94-413 Attention: Document Control Desk SPS/ETS:

Washington, DC. 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 SPECIFICATIONS CHANGES CORE OPERATING LIMITS REPORT Pursuant to 10 CFR 50.90, the Virginia Electric and Power Company requests amendments, in the form of changes to the Technical Specifications, to Facility Operating License Nos. DPR-32 and DPR-37 for Surry Power Station Units 1 and 2, respectively. Amendment 189 approved on March 2, 1994 for Surry Units 1 and 2, removed fuel cycle-specific parameters from the Technical Specifications. The proposed changes will eliminate the remaining references to cycle-specific parameters in the Surry Technical Specifications.

Discussions of the proposed Technical Specifications changes are provided in Attachment 1. The proposed Technical Specifications changes are provided in Attachment 2. It has been determined that the proposed Technical Specifications 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 determination that these changes do not involve a significant hazards consideration is provided in Attachment 3. The proposed Technical Specifications changes have been reviewed and approved by the Stations Nuclear Safety and Operating Committees and the Management Safety Review Committee.

Should you have any questions or require additional information, please contact us.

Very truly yours, r1A~~/?c~DJ----

1a;;,' ~'Hanlon Senior Vice President - Nuclear Attachments

- - - - 1: C _;:_:_ ..~ c~~.t-~. __ -

94071. 90369 940714---

PDR ADDCK 05000280 p PDR

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 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.

Acknowledgecfbefore me this _L!/_ day of , 19%

My Commission Expires: C..d?";Jc: ,5(

(SEAL}

Attachment 1 Discussion of Changes Surry Power Station

  • Discussion of Changes e

Background

Generic Letter 88-16, "Removal of Cycle-Specific Parameter Limits from Technical Specifications," dated October 4, 1988, provided the guidance for preparation and submittal of a license amendment to remove the fuel cycle-specific parameters from Technical Specifications. Virginia Electric and Power Company submitted a license amendment request on July 2, 1993 to eliminate fuel cycle-specific parameters.

License amendment 189 for Surry Power Station Units 1 and 2, which removed the cycle specific parameter limits, was granted on March 2, 1994. However, Technical Specification Figures 3.12.1 A and 1B, Control Bank Insertion Limits for Normal 3 Loop Operation, for Units 1 and 2 respectively, were not deleted as identified in the body of the letter. In addition, a reference to Figures 3.12.1 A and 1B was inadvertently included in Technical Specification 3.12.A.2 in a separate license action which was concurrently being processed. Therefore, a Technical Specification change is being requested to correct the administrative errors.

Specific Changes Technical Specification 3.12.A.2 is changed to read as follows:

Whenever the reactor is critical, except for physics tests and control rod assembly surveillance testing, the full length control banks shall be inserted no further than the appropriate limit specified in the CORE OPERATING LIMITS REPORT. With a control bank inserted beyond the limit specified in the CORE OPERATING LIMITS REPORT, restore the control rod assembly bank to within its limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, or reduce THERMAL POWER within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to less than or equal to that fraction of RATED POWER which is specified in the CORE OPERATING LIMITS REPORT, or place the reactor in HOT SHUTDOWN within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

Technical Specification Figures 3.12.1 A and 1B, "Control Bank Insertion Limits for Normal 3 Loop Operation," for Units 1 and 2 are deleted from the Technical Specification.

Page 1 of 2

Safety Significance

  • Removal of the remaining references to fuel cycle-specific parameter limits from Technical Specifications and incorporation of these parameters into a COLR is administrative in nature. The removal of cycle specific parameters from the Technical Specifications was previously considered in Amendment 189 to have no impact on plant operation or safety. No safety-related equipment, safety function, or plant operation characteristic will be altered as a result of the removal of cycle specific parameters from the Technical Specifications. Removing the control bank insertion limits from the Technical Specifications and the reference to these figures was intended in Amendment 189 and therefore is presently an administrative change.

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