ML20198F897
| ML20198F897 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 12/16/1998 |
| From: | Berkow H NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20198F903 | List: |
| References | |
| NUDOCS 9812280245 | |
| Download: ML20198F897 (12) | |
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'4 UNITED STATES
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j NUCLEAR REGU1.ATORY COMMISSION i
e WASHINGTON, D.C. ace 6H001 s.,*****/
VIRGINIA ELECTRIC AND POWER COMPANY t
DOCKET NO. 50-280 SURRY POWER STATION. UNIT NO.1 l
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 217 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 September 12,1996, as supplemented April 24,1997, and September 24,1998, 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.
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9812290245 981216 PDR ADOCK 05000280 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.B of Facility Operating License No. DPR-32 is hereby amended to read as follows:
(B)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 217, are hereby incorporated in the license. The licensee shall operato the facility in accordance with the Technical Specifications.
3.
Further, Facility Operating License No. DPR-32 is hereby amended to revise Condition 3.1 as follows:
3.1 The licensee shallimplement and maintain in effect the provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report and as approved in the SER dated September 19,1979, (and Supplements dated May 29,1980, October 9,1980, December 18,1980, February 13,1981, December 4,1981, April 27,1982, November 18,1982, January 17,1984, February 25,1988, and July 23,1992), and the Safety Evaluation issued December 16
,1998, for Technical Specification Amendment No. 217 subject to the following provision:
The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
4.
This license amendment is effective as of its date of issuance and shall be implemented within 75 days.
FOR THE NUCLEAR REGULATORY COMMISSION b
s rbert N. B rk w, Director roject Directorate ll-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
- 1. Page 5 of License DPR-32
- 2. Changes to the Technical Specifications Date of issuance: December 16, 1998
~
. H The licensee shall maintain in effect and fully implement all provisions of the Commission-approved physical security plan, including amendments and changes made pursuant to the authority of 10 CFR 50.54(p). The approved security plan consists of documents withheld from public disclosure pursuant to 10 CFR 2.790(d), referred to as Surry Power Station, Unit Nos.1 and 2 Physical Security Plan, dated November 30, 1977, as revised September 25,1978, supplemented (Chapter 10) October 25,1978, revised January 1.2,1979, and supplemented February 16,1979.
3.1 The licensee shallimplement and maintain in effect the provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report and as approved in the SER dated September 19,1979, (cnd Supplements dated May 29, 1980, October 9,1980, December 18,1980, February 13,1981, December 4,1981, April 27,1982, November 18,1982, January 17,1984, February 25,1988, and July 23, 1992), and the Safety Evaluation issued becember 16
,1998, for Technical Specification Amendment No. 217 subject to the following provision:
The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
3.J The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to t;w authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain Safeguarde information protected under 10 CFR 73.21, are entitled: "Surry Power Station Physical Security Plan," with revisions submitted through February 24,1988; "Surry Power Station Guard Training and Qualification Plan," with revisions submitted through May 29,1987; and "Surry Power Station Safeguards Contingency Plan," with revisions submitted through January 9,1987. Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.
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UNITED STATES g
j NUCLEAR REGULATORY COMMISSION
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VIRGINIA ELE.CTRIC AND POWER COMPANY DOCKET NO. 50-281 SURRY POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 217 License No. DPR-37 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated September 12,1996, as supplemented April 24,1997, and September 24,1998, 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.
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. 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 1
Operating License No. DPR-37 is hereby amended to read as follows:
(B)
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 217, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
Further, Facility Operating License No. DPR-37 is hereby amended to revise Condition 3.1 as follows:
3.1 The licensee shall implement and maintain in effect the provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report and as approved in the SER dated September 19,1979, (and Supplements dated May 29,1980, October 9,1980, December 18,1980, February 13,1981, December 4,1981, April 27,1982, November 18,1982, January 17,1984, February 25,1988, and July 23,1992), and the Safety Evaluation issued December 16
,1998, for Technical Specification Amendment No. 217 subject to the following provision:
The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
4.
This license amendment is effective as of its date of issuance and shall be implemented within 75 davs.
FOR THE NUCLEAR REGULATORY COMM SSION Her ert N. Berk
, Director Project Directorate ll-2 Division of Reactor Projects - 1/ll Office of Nuclear Reactor Regulation
Attachment:
- 1. Page 6 of License DPR-37
- 2. Changes to the Technical Specifications Date of Issuance: December 16, 1998
. H The licensee shall maintain in effect and fully implement all provisions of the Commission-approved physical security plan, including amendments and changes made pursuant to the authority of 10 CFR 50.54(p). The approved security plan consists of documents withheld from public disclosure pursuant to 10 CFR 2.790(d), referred to as Surry Power Station, Unit Nos.1 and 2 Physical Security Plan, dated November 30, 1977, as revised September 25,1978, supplemented (Chapter 10) October 25,1978, i
revised January 12,1979, and supplemented February 16,1979.
3.1 The licensee shall implement and maintain in effect the provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report and as approved in the SER dated September 19,1979, (and Supplements dated May 29, 1980, October 9,1980, December 18,1980, February 13,1981, December 4,1981, April 27,1982, November 18,1982, January 17,1984, February 25,1988, and July 23, 1992), and the Safety Evaluation issued December 16,1998, for Technical Specification Amendment No. 217 subject to the following provision:
The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
3.J The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain Safeguards information protected under 10 CFR 73.21, are entitled: "Surry Power Station Physical Security Plan," with revisions submitted through February 24,1988; "Surry Power Station Guard Training and Qualification Plan," with revisions submitted through May 29,1987; and "Surry Power Station Safeguards Contingency Plan," with revisions submitted through January 9,1987. Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.
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BACHMENTTO LICENSE AMENDMENT AMENDMENT NO. 217 TO FACILITY OPERATING LICENSE NO. DPR-32 AMENDMENT NO 217 TO FACILITY OPERATING LICENSE NO. DPR-37
- DOCKET NOS. 50-280 AND 50-281 Revise Appendix A as follows:
l Remove Paoes insert Paaes TSii TSli TS lii TS iii TS 3.21-1 TS 3.21-2 TS 3.21-3 TS 3.21-4 TS 3.21-5 TS 3.21-6 TS 3.21-7 TS 3.21-8.
TS 3.21-9 TS 4.18-1 TS 4.18-2 TS 4.18-3 TS 4.18-4 TS 4.18-5 TS 4.18-6 TS 4.18-7 TS 6.1-3 TS 6.1-3 TS 6.1-8 TS 6.1-8 L TS 6.4-4 TS 6.4-4 l-l I
i
.7 TSii
[.
TECHNICAL SPECIFICATION TABLE OF CONTENTS l
SECTION TITLE PAGE
'3.15 DELETED 3.16 EMERGENCY POWER SYSTEM TS 3.16-1 3.17 LOOP STOP VALVE OPERATION TS 3.17-1 3.18 MOVABLE INCORE INSTRUMENTATION TS 3.18-1 3.19 MAIN CONTROL ROOM BOTTLED AIR SYSTEM
. TS 3.19-1 3.20 SHOCK SUPPRESSORS (SNUBBERS)
TS 3.20-1 3.21 DELETED l
3.22 AUXILIARY VENTILATION EXHAUST FILTER TRAINS TS 3.22-1 3.23 CONTROL AND RELAY ROOM VENTILATION SUPPLY FILTER TS 3.23-1 TRAINS 4.0 SURVEILLANCE REOUIREMENTS TS 4.01 4.1 OPERATIONAL' SAFETY REVIEW TS 4.1-1 4.2 AUGMENTED INSPECTIONS TS 4.2-1 4.3 ASME CODE CLASS 1,2, AND 3 SYSTEM PRESSURE TESTS TS 4.3 1 4.4 CONTAINMENT TESTS TS 4.4-1 4.5 SPRAY SYSTEMS TESTS TS 4.5-1 4.6 EMERGENCY POWER SYSTEM PERIODIC TESTING TS 4.6-1 4.7 MAIN STEAM LINE TRIP VALVES TS 4.7-1 4.8 AUXILIARY FEEDWATER SYSTEM TS 4.8-1 4.9 RADIOACTIVE GAS STORAGE' MONITORING SYSTEM TS 4.9-1 4.10 REACTIVITY ANOMALIES TS 4.10-1 4.11 SAFETY INJECTION SYSTEM TESTS TS 411-1 l'
4.12 VENTILATION FILTER TESTS TS 4.12-1 L
'4.13 DELETED 4.14 -DELETED Amendment Nos. 217 and 217
TS iii
'ECHNICAL SPECIFICATION TABLE OF CONTENTS SECTION TITLE PAGE 4.15 AUGMENTED INSERVICE INSPECTION PROGRAM FOR HIGH TS 4.15-1 ENERGY LINES OUTSIDE OF CONTAINMENT 4.16 LEAKAGE TESTING OF MISCELLANEOUS RADIOACTIVE TS 4.16-1 MATERIALS SOURCES 4.17 SHOCK SUPPRESSORS (SNUBBERS)
TS 4.17-1 i
4.18 DELETED l
4.19 STEAM GENERATOR INSERVICE INSPECTION TS 4.19-1 4.20 CONTROL ROOM AIR FILTRATION SYSTEM TS 4.20-1 5.0 DESIGN FEATURES TS 5.1-1 5.1 SITE TS 5.1-1 5.2 CONTAINMENT TS 5.2-1 5.3 REACTOR TS 5.3-1 5.4 FUEL STORAGE TS 5.4-1 6.0 ADMINISTRATIVE CONTROLS TS 6.1-1 6.1 ORGANIZATION, SAFETY AND OPERATION REVIEW TS 6.1-1 6.2 GENERAL NOTIFICATION AND REPORTING REQUIREMENTS TS 6.2-1 6.3 ACTION TO BE TAKEN IF A SAFETY LIMIT IS EXCEEDED TS 6.3-1 6.A UNIT OPERATING PROCEDURES TS 6.4-1 6.5 STATION OPERATING RECORDS TS 6.5-1 6.6 STATION REPORTING REQUIREMENTS TS 6.6-1 6.7 ENVIRONMENTAL QUALIFICATIONS TS 6.7-1 6.8 PROCESS CONTROL PROGRAM AND OFFSITE DOSE TS 6.8-1 CALCULATION MANUAL Amendment Nos. 217 and 217
TS 6.1-3
- 7.
Deleted.
8.-
Deleted.
- 9.
The health physics technician requirement of Specification 6.1.B.5 may not be met for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate an unexpected absence provided immediate action is taken to fill the required position.
10.
Procedures will be established to insure that NRC policy statement guidelines regardmg working hours established for employees are followed. In addition, procedures will provide for documentation of authorized deviations from those guidelines and that the documentation is available for NRC review.
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Amendment Nos. 217 and 217 l
TS 6.1-8
,c 9.
Deleted.
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- 10. Deleted.
- 11. Review of every unplanned onsite release of radioactive material to the environs exceeding the limits of Specification 3.11, 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.
- 13. Review of the Fire Protection Program and implementing procedures and shall submit recommended Program changes to the designated offsite management responsible for reviewing changes that pertain to Fire Protection.
g.
Authority The SNSOC shall:
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 md the Site Vice President; however, the Site Vice President shall have responsibility for resolution of such disagreements pursuant to 6.1.A above.
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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. 217 and 217 l
- _-7_
TS 6.4-4 L*
D. All procedures described in Specifications 6.4.A and 6.4.B shall be followed.
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E. The facility Fire Protection Program and implementing procedures which have been L
l established for the station shall be implemented and maintained.
F. Deleted l
G. In cases of emergency, operations personnel shall be authorized to depart from approved procedures where necessary to prevent injury to personnel or damage to the facility. Such changes shall be documented, reviewed and approved by the Station Nuclear Safety and Operating Committee.
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Amendment Nos. 217 and 217
-