ML18153C803
| ML18153C803 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna  |
| Issue date: | 11/07/1991 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML18153C804 | List: |
| References | |
| 91-661, NUDOCS 9111140022 | |
| Download: ML18153C803 (7) | |
Text
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 November 7, 1991 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS 1 AND 2 SURRY POWER STATION UNITS 1 AND 2 PROPOSED TECHNICAL SPECIFICATION CHANGES Serial No.91-661 NAPS/JYR Docket Nos. 50-338 50-339 50-280 50-281 License Nos. NPF-4 NPF-7 DPR-32 DPR-37 Pursuant to 1 O CFR 50.90, the Virginia Electric and Power Company requests amendments, in the form of changes to the Technical Specifications, to Operating License Numbers NPF-4 and NPF-7 for North Anna Power Station Units 1 and 2, respectively and to Operating License Numbers DPR-32 and DPR-37 for Surry Power Station Units 1 and 2, respectively. The proposed changes will revise the current Technical Specifications to ensure our accredited training programs are adequately reflected therein.
A discussion of the proposed changes is provided in Attachment 1.
The proposed changes are presented in Attachment 2 for North Anna Units 1 and 2 and in Attachment 3 for Surry Units 1 and 2.
This request has been reviewed by the Station Nuclear Safety and Operating Committee and the Management Safety Review Committee.
It has been determined that this request does not involve an unreviewed safety question as defined in 1 O CFR 50.59 or a significant hazards consideration as defined in 1 O CFR 50.92.
The basis for our determination that no signification hazards consideration is involved is presented in Attachment 4.
- S"iiTil.40022 91. n~.
PDR ADOCK 05000280 p
Should you have any questions or require additional information, please contact us at your earliest convenience.
W. L. St wart Senior Vice President - Nuclear Attachments
- 1.
Discussion of Proposed Changes
- 2.
Proposed Technical Specification Change for North Anna Units 1 and 2
- 3.
Proposed Technical Specification Change for Surry Units 1 and 2
- 4.
1 O CFR 50.92 Evaluation cc:
U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, N.W.
Suite 2900 Atlanta, GA 30323 Mr. M. S. Lesser NRC Senior Resident Inspector North Anna Power Station Mr. M. Branch NRC Senior Resident Inspector Surry Power Station Commissioner Department of Health Room 400 109 Governor Street Richmond, Virginia 23219
COMMONWEAL TH OF VIRGINIA )
)
COUNTY OF HENRICO
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The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by E. W. Harrell, 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 aµthorized 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 My Commission Expires:
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Discussion of Proposed Changes North Anna Units 1 and 2 Surry Units 1 and 2 Virginia Electric and Power Company
DISCUSSION OF PROPOSED CHANGES Introduction This section presents a discussion of the proposed Technical Specification changes presented in Attachments 2 and 3. These changes are applicable to the North Anna and Surry Units 1 and 2 Technical Specifications, respectively. These changes are being made to remove language describing, or committing to, any previous operator training programs since our training programs at North Anna and Surry have been accredited and certified in accordance with Regulatory Guide 1.8, Revision 2, "Qualification and Training of Personnel for Nuclear Power Plants."
Background
In May 1987 a revision to 1 O CFR 55, "Operators' Licenses," became effective.
Regulatory Guide 1.8, Revision 2, "Qualification and Training of Personnel for Nuclear Power Plants" provided specific guidance for implementing the revision to 1 O CFR 55.
These documents contain specific requirements for both initial and continuing (requalification) training of reactor operators, senior reactor operators and shift technical advisors.
The requirements specified in these documents supersede previous regulatory guidance specified on this issue (e.g., NUREG 0737, including the March 28, 1980 [Denton] letter to all licensees).
However, provisions of both documents allow the option to substitute accredited training programs for any other set of requirements, whether contained in 1 O CFR 55, a training program previously approved, or a licensing document (e.g., Technical Specifications or the UFSAR). This is summarized in Generic Letter 87-07 and NUREG-1262. In addition, NUREG 1262 states the following:
The approval is effective automatically, if you have an accredited program and have certified that it is based on a systems approach in accordance with GL 87-
- 07. You shouldn't expect to see any response from the Commission on changes that are implemented as a result of this rule, with the exception of any license amendments which are required because of something in your Technical Specifications.
There are a number of facilities that have a more restrictive requirement in their Technical Specifications than that for which they would have to apply; amending their Technical Specifications to obtain relief is permitted under the rule.
It would be an administrative change in order to conform with the Regulation. But it would not have to be acted on within 60 days and would be processed as any routine change to the Technical Specifications.
North Anna Power Station achieved accreditation for its training programs for both initial licensing and requalification training of operators and senior operators on October 24, 1985.
Surry Power Station achieved accreditation for its training programs for initial licensing and requalification training of operators and senior operators on November 14, 1985. Accreditation for the shift technical advisor training program was achieved on August 26, 1987 for both stations. Generic Letter 87-07 does require written notification from the licensee that the substitute programs are
accredited and, in the case of the requalification training program, certified to be based on a systems approach to training. Written notification of the accreditation of the operator training programs was made to the NRC in accordance with Generic Letter 87-07 by letter dated March 30, 1989.
Technical Specification Changes General The proposed Technical Specification changes described below specify if applicable
- to North Anna or Surry Power Station.
The changes described below are strictly administrative in nature, consistent with the guidance in NUREG-1262.
Technical Specification 6.3.1 - Applicable to North Anna This Specification was modified to delete the reference to the March 28, 1980 NRC letter and to substitute our accredited training programs (including Shift Supervisor, Assistant Shift Supervisor, Control Room Operator - Nuclear, and Shift Technical Advisor) for the previous Shift Technical Advisor requirements. The March 28, 1980 NRC letter only deals with programs that have since been superseded by accreditation and can therefore be deleted. The substitution of our accredited training programs for the previous Shift Technical Advisor requirements is due to the fact that the previous Shift Technical Advisor requirements have been superseded by an accredited program. This change also allows us to specify the remaining accredited programs.
Technical Specification 6.4.1 - Applicable to North Anna This Specification was modified to redefine the responsibilities of the Manager -
Nuclear Training.
As a result, the responsibility for ensuring retraining and replacement programs that have achieved accreditation and the responsibility for maintaining accreditation have been added to this Specification. Section 5 of ANS 3.1
. - (12/79 Draft) is still required for training programs that have not received accreditation. In addition, a footnote was added to reference any exceptions that the QA Topical Report may take from to ANS 3.1.
Technical Specification 6.1.B.1 - Applicable to Surry This Specification was modified to delete the reference to the March 28, 1980 NRC letter. The March 28, 1980 NRC letter only deals with programs that have since been superseded by accreditation and can therefore be deleted.
Technical Specification 6.1.B.2 - Applicable to Surry This Specification was modified to allow substitution of our accredited training programs (including Shift Supervisor, Assistant Shift Supervisor, Control Room Operator - Nuclear, and Shift Technical Advisor) for the previous Shift Technical
Advisor requirements. The substitution of our accredited training programs for the previous Shift Technical Advisor requirements is due to the fact that the previous Shift Technical Advisor requirements have been superseded by an accredited program.
This change also allows us to specify the remaining accredited programs.
Technical Specification 6.1.B.3 - Applicable to Surry This Specification was modified to redefine the responsibilities of the Manager -
Nuclear Training.
As a result, the responsibility for ensuring retraining and replacement programs that have achieved accreditation and the responsibility for maintaining accreditation have been added to this Specification. Section 5 of ANS 3.1
- (12/79 Draft) is still required for training programs that have not received accreditation.