ML20004B757
| ML20004B757 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 05/22/1981 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20004B758 | List: |
| References | |
| NUDOCS 8106010004 | |
| Download: ML20004B757 (25) | |
Text
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NUCLEAR REGULATORY COMMISSION 3.' e(
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WASHINGTON, D. C. 20556
%~u y VIRGI'11A ELECTRIC AND MWER COMPANY
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00CKET NO. 50-280 SURRY POWER STATION, UNIT NO.1 AMENDMENT TO FACILITY OPERAT!!iG LICENSE Amendment No. 69 L~icense No. DPR-32 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The applications for amendment by Virginia Electric and Power Company (the licensee) dated March 31, August 28, and November 14, 1980, as supplemented August 4,1980 and February 23, 1981, com' ply 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 applications, 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 attachmnt to this license amendment, and paragraph 3.B of Facility Opc.-ating License No. DPR-32 is hereby amended to read as follows:
(B) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amend. Tent No. 69, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This licente amendment is effective within 7 days of the date of issuance.
A FOR THE NUCLE { REGULATORY COPJ41SSION ub l..f h/
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. arga, v iof Operating Reactors < ranch #1 Division of Licens1
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 22, 1981
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VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 5:-281 SURRY POWER STATION, UNIT'NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 69 L~icense No. OFR-37
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1.
The Nuclear. Regulatory Commission (the Cc ission) has found that:
A.
The applications for amendment by Virginia Electric and Power Company (the licensee), dated March 31, August 28, and November 14, 1980, as supplemented August 4, 1980 and Februarp 23,1981, : comply 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 applwations, 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 comp'iance 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 Comission's regulations and all applicable requirements have been satisfied.
_ 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 Appendices A and B, as revised through Amendment No. 69, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective within 7 days of the date of issuance.
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teven\\N. Varga q C ief Operating Reacto Branch #1 Division of Lic sing
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 22, 1981 i
ATTACHMENT TO LICENSE AMENDMENTS NiENDMENT "0. 69 TO FACILITY OPERATING LICENSE NO. OPR-32 AMENDMENT NO. 69 TO FACILITY OPERATING LICENSE NO. DPR-37 DOCKET NOS. 50-280 AND 50-281 Revise Appendix A as follows:
Remove Pages Insert Pages 6.1-1 6.1-1 4
6.1-2a 6.1-2 6.1-2b 6.1-3 6.1-3 6.1-4 6.1-4 6.1-5 6.1-5 6.'l -6 6.1-6 8
6.1-7
.6.1-7 6.1-8 6.1-8 6.1-9 6.1-9 6.1-10 6.1-10 6.1-11 6.1-11 6.1-12 6.1-12 6.1-13 6.1-14 6.1-15 T.S. Fig. 6.1-1 T.S. Fig. 6.1-1 T.S. Fig. 6.1-2 T.S. Fig. 6.1-2 T.S. Fig. 6.1-3 l
6.2-1 6.2-1 6.3-1 6.3-1 6.4-5 6.4-5 i
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TS 6.1-1 6.0 ADMINISTRATIVE CONTROLS 6.1 ORGANIZATION, SAFETY AND OPERATION REVIEW Specification A.
The Station Manager shall be responsible for the safe operation of the facility. In his absence, the Assistant Station Manager shall be responsible for t.he rafe operation of the facility. During the absence of both, the Station Manager shall delegate in writing the succession to this responsibility.
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1.
The offsite organization for facility management and technical support shall be as shown on TS Figure 6:1-1.
B.
The Station orgat.ization shall conform to the chart as shown on TS Figure 6.1-2.
1.
Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N.18.1-1971 for comparable positions, and the supplemental requirements specified in the March 20, 1980 NRC letter to all licensees, except for the Supervisor-Health Physics who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.
Amendments 69 & 69
TS 6.1-2 2.
The Shift Technical Advisor shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design and response and analysis of tha. plant for transients and accidents.
3.
The Station Manager is responsib'e for ensuring that retraining and replacement training programs for the facility staff are maintained and that such programs meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55 and the supplemental requirements specified in the March 28, 1980 NRC letter to all licensees, and shall include familiarization with relevant industry operational experience i
identified by the SEC staff.
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.
Amendments 69 & 69
TS 6.1-3 7.
A Fire Brigade of at least five members, all of whom have receised fire service training, will be maintained on-site at all times.
This excludes personnel in Table 6.1-1 of the minimca shift crew necessary for safe shutdown of the plant and any personnel required for other essential functions during a fire emergency.
8.
A training program for the Fire Brigade shall be maintained under the direction of a Fire Marshall and shall meet or exceed the requirements of the NFPA Code Section 27 (1975), except that a training session and drill shall be held at least once per 92 days.
9.
The health physics technician and Fire Brigade composition of Specifi-a cations 6.1.B.5 and 6.1.B.6 may be less than the minimum requirement f'or 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 accomodate unexpected absence provided immediate ac*. ion is taken to fill the required positions.
1 Ame.qdments 69 & 69
TS 6.1-4 TABLE 6.1-1 I
i MINIMLT SHIFT CR~7 COMPOSITION POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION ONE UNIT TWO UNITS
'IVO UNITS IN COL' OPERATING OPERATING SHUTDOWN OR REFUELING SS 1
1 1
SRO 1
1 None RO 5
3 2
A0 3
3 3
STA 1
1 None l
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i Amendments 69 & 69
TS 6.1-5 TABLE 6.1-1 (Continued)
Shift Supervisor with a Senior Reactor Operators License.
Individual with a Senior Reactor Operators License.
Individual with a Reactor Operators License.
RO Auxiliary Operator AO Shift Technical Advisor STA Except for the Shift Supervisor, the Shift Crew Composition may be one less than the minimum requirements of Table 6.1-1 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 accomodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the Shift Crew Composition to within tre minimum requirements of Table 6.1-1.
This provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crewman being late or absent.
During any absence of the Shift Supervisor from the Control Room while the unit is in operation, an individual (other than the Shift Technical Advisor) with a valid SRO license shall be designated to assume the Control Room command function. During any absence of the Shift Supervisor from the Control Room while the unit is shutdown or refueling, an individual with a valid R0 license (other than the Shift Technical Advisor) shall be designated to assume the Control Room command functions.
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Amendments 69 & 69 l
TS 6.1-6 C.
Organization units to provide a continuing review of the operational and safety aspects of the nuclear facility chall be constituted and have the authority and responsibilities outlined below:
1.
Station Nuclear Safety and Operating Committee a.
Function i
The SNSOC shall function to advise the Station Manager on all matters related to nuclear safety.
b.
Composition The SNSOC shall be composed of the:
Chairman:
Station Manager Vice Chairman:
Assistant Station Manager 4
i Member:
Superintendent-Operations Member:
Superintendent-Maintenance Member:
Superintendent-Technical Services Member:
Supervisor-Health Physics i
c.
Alternates All alternate members shall be appointed in writing by the SNSOC Chairman to serve on a temporary basis; how3ver, no more than two alternates shall participate as voting members in SNSOC activities at any one time.
d.
Meeting Frequency i
The SNSOC shall meet at least once per calendar mcenth and as convened by the SNSOC Chairman or his designated alternate.
e.
Quorum A quorum of the SNSOC shall consist of the Chairman or Vice Chairman and two members including alternates.
Amendments 69 & 69 i
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TS 6.1-7 f.
Responsibilities The S." SOC shall be responsible for:
1.
Review of 1) all proposed normal, abnormal, and emergency operating procedures and all proposed maintenance pro-cedures and changes thereto, 2) any other proposed procedures or changes thereto as determined by the Station Ma..ager which affect nuclear safety.
2.
Review of all proposed test and experiment procedures and results thereof when applicable.
3.
Review of proposed changes to Technical Specifications.
4.
Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.
5.
Investigation of all violations of the Technical Specifi-cations including the preparation and forwarding of reports covering evaluation and recommendations to prevent re-currence to the Manager-Nuclear Operations and Maintenance and to the Director-Safety Evaluation and Control.
6.
Review of events requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notification to the Commission.
7.
Review of facility operations to detect potential nuclear safety haza rds~.
8.
Performance of special reviews, investigations or analyses and report thereon as requested by the Chairman of the Station Nuclear Safety and Operating Committee.
Amendments 69 & 69
TS 6.1-8 9.
Review of the Plant Security Plan and implementing procedures and shall submit recommended changes to the Chairman of the Station Nuclear Safety and Operating Committee.
10.
Review of the Emergency Plan and implementing procedures and shall submit recommanded changes to the Chairman of the Station Nuclear Safety and Operating Committee.
g.
Authority The SNSOC shall:
1.
Recommend to the Station Manager written approval or dis-approval of items considered under (1) through (4) above.
2.
Render determinations in writing with regard to whether or not i
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 Manager-Nuclear Operations and Maintenance and the Director-Safety Evalaation and Control of disagreement between SNSOC and the Station Manager; however, the Station Manager shall have responsibility for resolution of such disagreements pursuant to 6.1-A above, b.
Records The SNSOC shall maintain written minutes of each meeting and copies
' hall be provided to the Manager-Nuclear Operations and Maintenance and to the Director-Safety Evaluation and Control.
Amendments 69 & 69
TS 6.1-9 2.
Safety Evaluation.nd Control (SEC) a.
Frnction 9
SEC shall function to provide independent review of designated activities in the areas of:
1.
Nuclear power plant operations 2.
Nuclear engineering 3.
Chemistry and radiochemist'y r
4.
Met:llurgy 5.
Instrumentation and Control 6.
Radiological safety 7.
Mechanical and electrical engineering I
8.
Administrative controls and quality assurance practices 9.
Other appropriate fields associated with the unique charac-teristics of the nuclear power plant b.
Composition The SEC staff shall be composed of the Director-Safety Evaluation and Control and a minimum of three individuals who qualify as staff
~
specialists. Each SEC staff specialist shall have an academic degree in ar..agineering or physical science field and, in addition, shall have a minimum of five years technical experience in one or more areas given in Specification 6.1.C.2.a.
These staff specialists shall not be directly involved in the licensing function.
c.
Consultants Consultants shall be hiilized as determined by the Director-Safety Evaluation and Control t: provide expert advice to SEC.
Amendments 69 & 69 1
TS 6.1-10 4
d.
Meeting Frequency The SEC staff shall meet at least once per calendar month for the purpose of fostering interaction of reviews regarding safety-related operational activities.
e.
Review The following subjects shall be reviewed by SEC:
1.
Written safety evaluations of changes in the stations as described in the Safety Analysis Report, changes in procedures as described in the Safety Analysis Report, and tests or experiments not described in the Safety Analysis Report which are completed with-out prior NRC approval under the provisions of 10 CFR 50.59 (a)(1).
This review is to verif; that such changes, tests, or experiments i
did not involve a change in the Technical Specifications or an unreviewed safety question as defined in 10 CFR 50.59 (a)(2) and 1
is accomplished by review of minutes of the Station Nuclear Safety and Operating Committee and the design change program.
2.
Proposed changes in procedures, proposed changes in the station, or proposed tests or experiments, any of which may involve a change in the Technical Specifications or an unreviewed safety question as defined in 10 CFR 50.59 (a)(2). Matters of this kind shall be referred to the Director-Safety Evaluation and Control l
by the Station Nuclear Safety and Operating Committee following l
its review prior to implementation.
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l Amendments 69 & 69 r
TS 6.1-11 3.
Changes in the Technical Specifications or license amendments relating to nuclear safity prior to implementation except in those cases where the change is identical to a previously reviewed proposed change.
4.
Violations and reportable occurrences such as:
(a) Violations of applicable codes, regulations, orders, Technical Specifications, license requirements or internal procedures or instructions having safety significance; I
(b) Significant operating abnormalities or deviations from normal or expected performance of station safety-related structures, systems, or components; and (c) Reportable occurrences as defined in the station Technical Specification 6.6.2.a.
Review of events covered under this paragraph shall include the results of any investigations made and the recommendations resulting from such investigations to prevent or reduce the probability of recurrence of the event.
5.
The Quality Assurance audit program at least once per 12 months and audit reports.
Amendments 69 & 69
TS 6.1-12 6.
Any other matter involving safe operation of the nuclear power stations which is referred to the Director-Safety Evaluation and Control by the Station Nuclear Safety and Operating Committee.
7.
Reports and meeting minutes of the Station Nuclear Safety and Operating Committee.
e.
Authority J
P-The Director-Safety Evaluation and Control shall report to and i
advise the Manager-Nuclear Technical Services, who shall advise the i
Vice President-Nuclear Operations on those areas of responsibility specified in Section 6.1.C.2.d.
f.
Records Records of SEC activities required by Specification 6.1.C.2.e shall be prepared and maintained in the SEC files and a summary shall be disseminated as indicated below each calendar month.
1.
Vice President-Nuclear Operations 2.
Nuclear Power Station Managers 3.
Manager-Nuclear Operations and Maintenance 4.
Manager-Nuclear Technical Services 5.
Manager-Quality Assurance, Operations 6.
Others that the Director-Safety Evaluation and Control may designate.
l Amendments 69 & 69
TS 6.1-13 3.
Quality Assurance Department a.
Function The Quality Assurance Department shall function to audit statica activities. These audits shall encompass:
1.
The conformance of facility operation to provisions contained within the Technical S;ecifications and applicable license conditions at least one per 12 months.
2.
The performance, training and qualifications of the entire i
facility staff at least once per 12 months.
3.
The results of actions tr...en to corr?ct deficiencies occurring in facility equipment, structures, systems or method of opera-tion that affect nuclear safety at least one per 6 months.
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4.
The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix "B",
j at least once per 24 months.
5.
The Station Emergency Plan and implementing procedures at least once per 24 months.
Amendments 69 & 69
TS 6.1-14
~.
6.
The Station Security Plan and implementing procedures at least once per 24 months.
7.
Any other area of facility operation considered appropriate by the Executive Manager-Quality Assurance or the Senior Vice President-Power Operations.
8.
The Station Fire Protection Program and implementing procedure-.
at least once per 24 months.
9.
An independent fire protection and loss prevention program inspectior, cad audit shall be performed at least once per i
12 months utilizing either qualified offsite licensee person:.el or an outside fire protection firm.
10.
An inspection and audit of the fire protection and loss preven-tion program shall be performed by a qualified outside fire consultant at least once per 36 months.
b.
Authority The Quality Assurance Department shall report to and advise the i
{
l Executive Manager-Quality Assurance, who shall advise the Senior l
Vice President-Power Operations on those areas of responsibility l
specified in 6.1.C.3.a above, l
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Amendments 69 & 69 t
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TS 6.1-15 l-c.
Records I
Records of the Quality Assurance Department audits shall be prepared j
and maintained in the department files. Audit reports shall be disseminated as indicated below:
1.
Nuclear Power Station Manager 2.
Manager-Nuclear Operations and Maintenance 3.
Manager-Nuclear Technical Services 4.
Manager-Quality Assurance, Operations 5.
Director-Quality Assurance, Nuclear Operations 6.
Director - Safety Evaluation and Control i
7.
Supervisor of area audited 8.
Nuclear Power Station Resident Quality Control Engineer 4
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Amer.dments 69 & 69 I
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13i P00RORIBIBL Amendments 69 & 69
TS 6.2-1 6,2 ACTION TO BE TAIGN IN THE EVENT OF A REPORTABLE OCCURRENCE IN STATION OPERATION Specification A.
The following actions shall be taken for reportable occurrences:
1.
The Commission shall be notified and/or a report submitted pursuant l
to the requirements of Specification 6.6.
2.
Each reportable occurrence requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Commission shall be reviewed by the SNSOC and submitted to the Director-Safety Evaluation and Control and the Manager-Nuclear i
Operations and Maintenance.
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Amendments 69 & 69
_ _..,. _ -,., _ _ - ~
TS 6.3-1 6.3 ACTION TO BE TAKEN IF A SAFETY LIMIT IS EXCEEDED Specification A.
The following actions shall be taken in the event a Safety Limit is violated:
1.
The facility shall be placed in at least hot shutdown witnin one hour.
2.
The Safety Limit violation shall be reported to the Commission, the Manager-Nuclear Operutions and Maintenance, and the Director-Safety Evaluation and Control within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
s 3.
A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the SNSOC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.
4.
The Safety Limit Violation Report shall be submitted to the Commission, the Director-Safety Evaluation and Control, and the Manager-Nuclear Operations and Maintenance within 14 days of the violation.
Amendments 69 & 69
TS 6.4-5 1.
Administrative Station Manager 2.
Abnormal Superintendent-Operations 3.
Annunciator Superintendent-Operations 4.
Health Physics Supervisor-Health Physics 5.
Emergency Superintendent-Operations 6.
Maintenance Mechanical Supervisor Electrical Supervisor Instrument Supervisor 7.
Operating Superintendent-Operations 8.
Periodic Test Engineering Supervisor 9.
Start-up Test Engineering Supervisor 10.
Special Test Engineering Supervisor i
11.
Quality Assurance Resident-Quality Control Engineer 12.
Chemistry Supervisor-Chemistry Such changes will be documented as subsequently reviewed by the Station Nuclear Safety and Operation Committee and approved by the Station Manager.
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 and reviewed by the Station Nuclear Safety and Operating Committee and approved by the Station Manager.
Amendments 69 & 69
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