ML20249B817
| ML20249B817 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 06/19/1998 |
| From: | Kuo P NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20249B818 | List: |
| References | |
| NUDOCS 9806240261 | |
| Download: ML20249B817 (11) | |
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NUCLEAR REGULATORY COMMISSION R
WASHINGTON, D.C. 30086 4001 o
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- VIRGINIA ELECTRIC AND POWER COMPANY l
DOCKET NO. 50-280 SURRY POWER STATION. UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 215 License No. DPR-32 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated March 25,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations:
D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accorda'nce with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been sati.sfied.
9906240261 990619 PDR ADOCK 05000200 P
. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.8 of Facility Operating License No. DPR-32 is hereby amended to read as follows:
l (B)-
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 215, are he.iby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
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l ao-Tsin Kuo, Acting Director roject Directorate ll-1 Division of Reactor Projects - 1/ll l-Office of Nuclear Reactor Regulation
Attachment:
i Changes to the Technical Specifications Date ofissuance: June 19,1998 2
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UNITED STATES y
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30006 0001
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VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-281 SURRY POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 215 License No. DPR-37 i
l 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated March 25,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
7 l
i 2-2.
' Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility
- Operating License No. DPR-37 is hereby amended to read as follows:
(B)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 215, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technica! Specifications.
_ 3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
/
/
P o-Tsin Kuo, Acting Director roject Directorate 11-1 Division of Reacto-Projects - 1/ll Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date ofissuance:
June 19,1998
._.______,-.________._____..____m___.____
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ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 91s; TO FACILITY' OPERATING LICENSE NO. DPR-32 AMENDMENT NO. 215 TO FACILITY OPERATING LICENSE NO. DPR-37 DOCKET NOS. 50-280 AND 50-281 Revise Appendix A as follows:
Remove Paaes insert Paaes l
TS 6.1-1 TS 6.1-1 TS 6.1-6 TS 6.1-6 TS 6.1-7 TS 6.1-7 TS 6.1-8 TS 6.1-8 TS 6.8-1 TS 6.8-1 TS 6.8-2 TS 6.8-2 f
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TS 6.1-1 6.0 ADMINISTRATIVE CONTROLS 6.1 Organization. Safety and Operation Review Specification A. The Site Vice President shall be responsible for the overall operation of the facility. In his absence, the Manager - Station Operations and Maintenance shall be responsible for the safe operation of the facility. During the absence of both, the Site Vice President will delegate in writing the succession to this responsibility.
l An onsite and an offsite organization shall be established for facility operation and corporate management. The onsite and offsite organization shall include the positions for activities affecting the safety of the nuclear power plant.
- 1. Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through intermediate levels to and including all operating organization positions. These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and j
job descriptions for key personnel positions, or in equivalent forms of
)
I documentation. These requirements shall be documented in the UFSAR.
- 2. The Site Vice President shall be responsible for overall unit safe operation and l
shall have control over those onsite activities necessary for safe operation and maintenance of the plant.
l
- 3. The Vice President - Nuclear Operations shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining and providing technical support to the plant to ensure nuclear safety.
I I
- 4. The management position responsible for training of the operating staff and the i
position responsible for the quality assurance functions shall have sufficient organizational freedom including sufficient independence from cost and schedule when opposed to safety considerations.
I
- 5. The management position responsible for health physics shall have direct accessL to that onsite individual having responsibility for, overall facility management. Health physics personnel shall have the authority to cease any work activity when worker safety is jeopardized or in the event of unnecessary
. personnel radiation exposures.
Amendment Nos. 215 and 215
TS 6.1-6 C.
Organization units to provide a continuing review of the operational and safety aspects of the nuclear facility shall be constituted and have the authority and responsibilities outlined below:
1.
Station Nuclear Safety and Operating Committee (SNSOC) a.
Function The SNSOC shall function to advise the Site Vice President on all matters l
related to nuclear safety.
b.
Composition The SNSOC shall be composed of the:
Chairman: Manager - Station Safety and Licensing Vice Chairman and Member: Manager-Station Operations and Maintenance Member: Superintendent - Operations Member: Superintendent - Maintenance Member: Superintendent - Radiological Protection Member: Superintendent - Engineering c.
Altemates All alternate members shall be appointed in writing however, no more than two alternates shall participate as voting members in SNSOC activities at any one time.
d.
Meeting Freauency The SNSOC shall meet at least once per calendar month and as convened by the SNSOC Chairman or his designated alternate.
l e.
Ouorum -
A quorum of the SNSOC shall consist of the Chairman or Vice Chairman and two members including attemates.
Amendment Nos. 215 and 215
-. a TS 6.1 -
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f.
Responsibilities The SNSOC shall be responsible for:
1.
Review of a) all new normal, abnormal, and emergency operating procedures and all new maintenance procedures, b) all procedure changes that require a safety evaluation, and c) any other procedures or changes thereto as determined by the Site Vice President which affect nuclear l
safety.
2.
Review of all new test and experiment procedures that affect nuclear safety.
3.
Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.
4.
Review of proposed changes to Technical Specifications and shall submit recommended changes to the Site Vice President.
l 5.
Investigation of all violations of the Technical Specifications, including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Vice President - Nuclear Operations and to the Management Safety Review Committee.
6.
Review of all Reportable Events and special reports submitted to the NRC.
7.
Review of facility operations to detectpotential nuclear safety hazards.
8.
Performance of special reviews, investigations or analyses and report thereon as requested by the Chairman of the SNSOC or Site Vice j
President.
I
)
Amendment Nos. 215 and 215
TS 6.1-8 9.
Deleted.
- 10. Deleted.
- 11. Review of every unplanned onsite release of radioactive material to the environs exceeding the limits of Specification 3.ll, including the preparation of reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence and the forwarding of these reports to the Vice President - Nuclear Operations and to the Management Safety Review Committee.
- 12. Review of changes to the Process Control Program and the Offsite Dose Calculation Manual.
g.
Authority The SNSOC shall:
1 1.
Provide written approval or disapproval of items considered under (1) through (3) above. SNSOC approval shall be certified in writing by either the Manager - Station Operations and Maintenance or the Manager -
Station Safety and Licensing.
2.
Render determinations in writing with regard to whether or not each item considered under (1) through (5) above constitutes an unreviewed safety question.
3.
Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vice President -
Nuclear Operations and to the Management Safety Review Committee of disagreement between SNSOC and the Site Vice President; however, the Site Vic_e President shall have responsibility for resolution of such disagreements pursuant to 6.1.A above.
h.
Records The SNSOC shall maintain written minutes of each meeting and copies shall be provided to the Vice President - Nuclear Operations and to the. Management Safety Review Committee.
Amendment Nos. 215 and 215
TS 6.8-1 6.8 PROCESS CONTROL PROGRAM AND OFFSITE DOSE CALCULATION MANUAL A. Process Control Program (PCP)
Changes to the PCP:
- 1. Shall be documented and records of reviews performed shall be retained as required by Specification 6.5.B.12. This documentation shall contain:
l l
Sufficient information to support the change together with the appropriate a.
analyses or evaluations justifying the change (s) and
- b. A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.
- 2. Shall require review and acceptance by the SNSOC and the approval of the Site Vice President prior to implementation.
B. Offsite Dose Calculation Manual (ODCM) 1 Changes to th: ODCM:
- 1. Shall be documented and records of reviews performed shall be retained as required by Specification 6.5.B.12. This documentation shall contain:
Sufficient information to support the change together with the appropriate a.
analyses or evaluations justifying the change (s) and Amendment Nos. 215 and 215 i
[
... e TS 6.8-2
- b. A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302,40 CFR Part 190,10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
i
- 2. Shall require review and accel tance by the SNSOC and the approval of the Site Vice President prior to implementation.
- 3. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented.
l Amendment Nos. 215 and 215
.