ML18153C805

Revised Tech Specs 6.3 Re Facility Staff Qualifications, 6.4 Re Training & 6.1-2 Re Training Programs for Shift Supervisor,Assistant Shift Supervisor,Control Room Operator & Shift Technical Advisor

ML18153C805
Person / Time
Site:	Surry, North Anna
Issue date:	11/07/1991
From:	VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML18153C804	List: ML18153C803 ML18153C805
References
NUDOCS 9111140024
Download: ML18153C805 (8)

Text

Attachment 2 Proposed Technical Specification Change North Anna Units 1 and 2 Virginia Electric and Power Company

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6.3 ADMINISTRATIVE CONTROLS FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANS 3.1-(12/79 Draft)* for comparable positions, except for:

1. The Superintendent - Radiological Protection shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.

2. Incumbents in the positions of Shift Supervisor, Assistant Shift Supervisor (SRO), Control Room Operator - Nuclear (RO), and Shift Technical Advisor, shall meet or exceed the qualifications of the applicable training programs as accredited by the National Academy for Nuclear Training.

3. The Superintendent Operations shall hold (or have previously held) a Senior Reactor Operator License for North Anna Power Station or a similar design Pressurized Water Reactor plant.

4. The Supervisor Shift Operations shall hold an active Senior Reactor Operator License for North Anna Power Station.

6.4 TRAINING 6.4.1 The Manager - Nuclear Training is responsible for ensuring that retraining and replacement training programs for the facility staff are maintained and that such programs have achieved, and continue to maintain, accreditation by the National Academy for Nuclear Training. Retraining and replacement training programs shall meet the recommendations of Section 5 of ANS 3.1 (12/79 Draft)* for staff in positions for which no accredited program exists.

6.5 REVIEW AND AUDIT 6.5.1 STATION NUCLEAR SAFETY AND OPERATING COMMITIEE (SNSOC)

FUNCTION 6.5.1.1 The SNSOC shall function to advise the Station Manager on all matters related to nuclear safety.

• Exceptions to this requirement are specified in VEPCO's QA Topical Report, VEP-1, "Quality Assurance Program,.*Operational Phase" NORTH ANNA - UNIT 1 6-5

6.3 ADMINISTRATIVE CONTROLS FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANS 3.1-(12/79 Draft)* for comparable positions, except for:

1. The Superintendent - Radiological Protection shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.

2. Incumbents in the positions of Shift Supervisor, Assistant Shift Supervisor (SRO),Control Room Operator - Nuclear (RO), and Shift Technical Advisor, who shall meet or exceed the qualifications of the applicable training programs as accredited by the National Academy for Nuclear Training.

3. The Supervisor Shift Operations shall hold an active Senior Reactor Operator License for North Anna Power Station.

4. Incumbents in those positions for which training programs are accredited by the National Academy for Nuclear Training shall meet or exceed the minimum qualifications of the applicable training program guide.

6.4 TRAINING 6.4.1 The Manager - Nuclear Training is responsible for ensuring that retraining and replacement training programs for the facility staff are maintained and that such programs have achieved, and continue to maintain, accreditation by the National Academy for Nuclear Training. Retraining and replacement training programs shall meet the recommendations of Section 5 of ANS 3.1 (12/79 Draft)* for staff in positions for which no accredited program exists.

6.5 REVIEW AND AUDIT 6.5.1 STATION NUCLEAR SAFETY AND OPERATING COMMITTEE (SNSOC)

FUNCTION 6.5.1.1 The SNSOC shall function to advise the Station Manager on all matters related to nuclear safety.

• Exceptions to this requirement are specified in VEPCO's QA Topical Report, VEP-1, "Quality Assurance Prograrlll*Operational Phase" NORTH ANNA - UNIT 2 . 6-6

Attachment 3 Proposed Technical Specification Change Surry Units 1 and 2 Virginia Electric and Power Company

- TS 6.1-2 B. The facility organization shall conform to the following requirements:

1. Each member of the facility staff shall meet or exceed the minimum qualifications of ANS 3.1-(12/79 Draft) for comparable positions, except fqr: f

a. The Superintendent - Radiological Protection shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.

b. The Superintendent Operations shall hold (or have previously held) a Senior Reactor Operator License for Surry Power Station or a similar design Pressurized Water Reactor plant.

c. The Supervisor Shift Operations shall hold an active Senior Reactor Operator License for Surry Power Station.

2. Incumbents in the positions of Shift Supervisor, Assistant Shift Supervisor (SRO), Control Room Operator - Nuclear (RO), and Shift Technical Advisor, shall meet or exceed the qualifications of the applicable training programs as accredited by the National Academy for Nuclear Training.

3. The Manager - Nuclear Training is responsible for ensuring that retraining and replacement training programs for the facility staff are maintained and that such programs have achieved, and continue to maintain, accreditation by the National Academy for Nuclear Training.

Retraining and replacement training programs shall meet the recommendations of Section 5 of ANS 3.1 (12/79 Draft)* for staff in positions for which no accredited program exists.

4. Each on-duty shift shall be composed of at least the minimum shift crew composition for each unit as shown in Table 6.1-1.

5. A health physics technician shall be on site when fuel is in the reactor.

6. All core alterations shall be observed and directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.

• Exceptions to this requirement are specified in VEPCO's QA Topical Report, VEP-1, "Quality Assurance Program, Operational Phase" Amendment Nos. 1p'i and 1~

Attachment 4 10 CFR 50.92, No Significant Hazards Consideration North Anna Units 1 and 2 Surry Units 1 and 2 Virginia Electric and Power Company

10 CFR 50.92 Significant Hazards Considerations Analysis The proposed changes are being made to remove language describing, or committing to, any previous operator training programs since the 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."

The proposed changes delete reference to the March 28, 1980 NRC letter and substitute Virginia Electric and Power Company accredited training programs (including Shift Supervisor, Assistant Shift Supervisor, Control Room Operator -

Nuclear, and Shift Technical Advisor) for the previous training requirements.

In addition, the proposed changes redefine the responsibilities of the Manager -

Nuclear Training to encompass the responsibilities for ensuring retraining and replacement programs that have achieved accreditation and the responsibility for maintaining accreditation.

The proposed Technical Specification changes have been determined to administrative in nature.

It has a been determined that the proposed changes do not involve a significant hazards consideration as defined in 10 CFR 50.92. This determination was based on the following points.

1. Accident Probability or Consequence Increase. The proposed changes have no adverse impact upon potential accident probability or consequence. The proposed changes allow for substitution of regulatory requirements for training programs which have been accredited and certified. North Anna and Surry's training programs are accredited and certified as permitted by the regulation.

Likewise, the consequences of the accidents will not increase as a result of the proposed Technical Specification changes.

Therefore, the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.

2. Accident Probability Creation. The proposed changes allow for substitution of regulatory requirements for training programs which have been accredited and certified. North Anna and Surry's training programs are accredited and certified as permitted by the regulation. The proposed changes Therefore, the proposed changes will not create the possibility of a new or different kind of accident from any accident previously evaluated.

3. Safety Margin Reduction. The proposed changes allow for substitution of regulatory requirements for training programs which have been accredited and certified. North Anna and Surry's training programs

IT are accredited and certified as permitted by the regulation. Therefore, the proposed changes do not involve a reduction in the margin to safety.

Based on the above significant hazards consideration evaluation,, Virginia Electric and Power Company concludes that the activities associated with this proposed Technical Specification change satisfies the no significant hazards consideration standards of 10 CFR 50.92(c) and, accordingly, a no significant hazards consideration finding is justified.