ML20058B468

Amends 146 & 142 to Licenses DPR-32 & DPR-37,respectively, Replacing Independent/Operational Event Review Group W/Mgt Safety Review Committee

ML20058B468
Person / Time
Site:	Surry
Issue date:	10/18/1990
From:	Berkow H Office of Nuclear Reactor Regulation
To:
Shared Package
ML20058B471	List: ML20058B468 ML20058B479
References
NUDOCS 9010300219
Download: ML20058B468 (19)

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UNITED STATES T

- E' NUCLEAR REGULATORY COMMISSION n

I WAsHINoToN, D. C. 20555

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DOCKET NO. 50-280 SURRY POWER STATION, UNIT NO. 1 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 146 License No. OPR-32 j

1 1.'

The Nuclear Regulatory Commission (the Commission) has found that:

j A.

The application for amendment by Virginia Electric and Power i

Company (the licensee) dated February 1, 1990, as supplemented o'

July 30, 1990, complies with the standards and requirements of i

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 operat.e in conformity with the application;

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the provisions of the Act, and the rules and regulations of.the l

Commission; I

~ C.-

There is reasonable assurance (1) 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

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defense and security or to the health and safety of the-public; and 4

..:u E..

The; issuance of this amendment'is in accordance with,10 CFR'Part-t

. 51'of the Commission's regulations and alliapplicable' requirements

' Nf j have'been' satisfied.

l2.

Accordingly, the license is amended by changes to the Technical

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Specifications

as: indicated in'the attachment to this license

' amendment, and. paragraph 3.B of Facility Operating License

..No' 0PR-32-is hereby amended to: read as follows:.

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a-2 (B) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 146, are hereby incorporated in the license.

The licensee shall operate the facility in accordacea with the Technical Specifications.

3.-

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION P

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H rbert N. Berkow, Director Project Directorate II-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical

. Specifications 1Date of Issuance: October 18, 1990

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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. 142 License No. OPR-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 February 1, 1990, as supplemented July-30,-1990, <:omplies 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; 1

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 inimic.:1 to the common

. defense and security or to the. health and safety of the public;'

i a-

-and, j

'E.

The issuance of this amendment:is in accordance with 10 CFR Part I

51 of the: Commission's' regulations'and all applicable requirements

-have been satisfied.

2L 1 Accordingly, the license is amended by changes to the Technical Specifications'as indicated in the attachment to this license-i lE -

amendment,and paragraph 3.8 of Facility Operating License No.,DPR-37-is1herebyLamended to read as follows:

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1 (B) Teci.nical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 142, are hereby incorporated'in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

-3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION s

H r ert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulat'on P

Attachment:

Changes to the Technical

Specifications Date of-Issuance: October 18, 1990 J

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ATTALS4ENT TO LICENSE AMENDMENT AMENDMENT N0. 146 FACILITY OPERATING LICENSE NO. OPR-32 AMENDMENT NO. 142 FACILITY OPERATING LICENSE NO. OPR-37 DOCKET NOS. 50-280 AND 50-281 Revise Appendix A as follows:

Remove Pages Insert Pages TS 6.1-1 TS 6.1-1 TS 6.1-2 TS 6.1-?

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 6.1-8a TS 6.1-9 TS 6.1-9 thru TS 6.1-15 thru TS 6.1-13 TS 6.2-1 TS 6.2-1 TS 6.3-1 TS 6.3-1 t

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TS 6.1 t

. 6.0 i ADMINISTRATIVE CONTROLS 6.1-Oroanization. Safety and Ooeration Review Snecification A.

The Station Manager shall be responsible for the overall operation of the facility.. In his absence, the Assistant Station Manager (Operations and Maintenance) shall be responsible for the safe operation of the facility, During the absence of both, the Station Manager will delegate in writing the succession to this responsibility.

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 job descriptions for key ' personnel cositions, or in. equivalent forms of 1

- documentation. These equirements shall be documented in the UFSAR.

t 2.

The Station Manager shall be responsible for overall unit safe operation and shall have control over those on' site activities necessary for safe operation'and maintenance of the plant.

1 3.

The Vice President Nuclear Operations shall have

'l 1

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 i,

safety, j

. 4.

The management position responsible for training of the

-. operating staff.and the position ' responsible for the ' quality 4

assurance functions shall have ' sufficient organizational-

"j freedom? including-sufficient independence from< cost and-schedule when opposed to safety considerations.

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.The management position responsible.for, health physics i

shallthave direct; access to that onsite: Individual havinge responsibility for:overall facility" managementi, Health.

Physics'personnelishall.have the authority to cease any i

' work activity:when worker safety is jeopardized or in the.

event of unnecessary personnel radiation exposures.

y B.

Thel facility 1.organizationL 'shall conform to the following1 o

_ requirements:

i 1.-

.Each member of the facility staff.shall meet or exceed the

minimumiqualifications

of ANS; 3,1 (12/79L Draft)* for.

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comparable positions, and the supplemental requirements -

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specified in the March 28,1980.NRC' letter to all licensees, except.for the Superintendent Radiological Protection who~,

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?shall; meet or e;xceed.the qualifications of Regulatory Guide y

<1.8, September;1975D 9

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Exceptions toLthis requirement arelspecified in VEPCO's OATopicalL Report,

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• VEP 1','" Quality Assurance Program, Operat$ns Phase."

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" Amendment. Nos. 3146' and 1142, f

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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 the plant for transients and accidents.

3.

- The Manager - Nuclear Training is responsible for ensuring l 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 ANS 3.1 (12/79 Draft)* 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 identified by the operatirig experience program. l 4.

Each on duty shift shcIl be composed of at least the minimum shift crew composition for each unit as shown in

' Table 6.1 1.

F 5.

A health physics technician shall be on slie when fuelis in the reactor, a

~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'-

1 no other concurrent responsibilities during this operation.

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v Exceptions to' this requirement are.specified'in VEPCO's OA Topical Report,-

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VVEP-1, " Quality Assurance Program, Operations Phase "

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M iAmendment Nos. 146 f and L142.,

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i TS 6.16 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 responsib!!ities outlined below:

i 1.

Station Nuclear Safety and Ooeratino Committee (SNSOC) a.

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

b.

Comoosition g

The SNSOC shall be composed of the:

Chairman: Assistant Station Manager, Nuclear Safety and Licensing Vice Chairman and Member: Assistant Station Manager, Operations and l

Maintenance Member: Superintendent - Operations Member: Superintendent Maintenance Member: Superintendent Radiological Protection Member: Superintendent Engineering

. c.

Afternates Y

' 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.

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' Meetina Frecuencv' H

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. The SNSOC shall meet at least once per calendar month'and as 1

convened by the SNSOC Chairman or his designated alternate.

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. Quorum.

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A quorum of the SNSOC shall consist of the Chairman or Vice ie 1

- Chairman and two; members including alternates.

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Amendment Nos.146,- andCl42,

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TS 6.1-7 f.

Responsibilities The SNSOC shall be responsible for:

1.

Review of.a) all proposed normal, abnormal, and emergency operating procedures and all proposed maintenance procedures and changes thereto, b) any other proposed procedures or changes thereto as determined by the Station Manager which affect nuclear safety.

t 2.

Review of all proposed 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 Station Manager.

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.

j 7.

Review of facility. operations to detect' potential nuclear safety hazards.

8.

. Performance of special reviews,-investigations or analyses and-report thereon as requested by the Chairman of the:SNSOC or -

. Station Manager.

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Amendment Nos. 146f and 142, 4

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TS 6.18

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9.

Review of the Plant Security Plan and implementing procedures and shall submit recommended changes to the Station Manager.

10.

Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the Station Manager.

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 c

Review Committee.

12.

Review of changes to the Process Control Program and the Offsite Dose Calculation Manual.

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Authority l

ine SNSOC shall:

1.

Provide written approval or disapproval of items considered under (1) through;(3) above, SNSOC' approval shall be certified in writing by an Assistant Station Manager.

' 2..

Render determinations in writing with regard to whether.or not each item. considered under (1) through (5) above co'stitutes anl-j unreviewed safety question.

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3.-

Provide written notification within 24' hours to the Vice President -

. Nuclear Operations and'to the Management Safety Review Committee of. disagreement betweeh'SNSOC and the Station Manager; hcwever, the Station Manager shall have responsibility J

for resolution of such disagreements pursuant to'6.1;A above.

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Records..

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The,SNSOC shall maintain written minutes'of each meeting and copies

. shal'l be provided to;the Vice President - Nuclear. Operations and to the y

LManagement Safety Re"iew Committee.

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Amendment Nos.,146. and 142, '

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2.

MANAGEMENT SAFETY REVIEW COMMITTEE (MSRC) a.

Function The Management Safety Review Committee shall function to provide I

independent review and audit of designated activities in the areas of:

1.

Station Operations 2.

Maintenance 3.

Reactivity Management 4.

Engineering 5.

Chemistry and Madiochemistry 6.-

Radiological Safety 7.

Quality Assurance Practices 8.

Emergency Preparedness 1 b.

Composition m

The MSI. ' shall be composed of the MSRC Chairman and a minimum of four MSRC members.

The Chairman and all members of the MSRC shall have u

. qualifications. that meet ' the requirements of Section 4.7 of ANS 3;1-

_(12/1979 ' Draft) ~

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Alternates

'All alternate members' shall be appointed = in. Writing by' the MSRC "hmrman to. serve. on a temporary ~ basis; however, no

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~more than - two alternates: shall participate as voting members

'in MSRC activities at any one time.

'd.

Consultants s

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.Consultaats"should be1 utilized as: determined. by: the, MSRC

" y-Chairman to provide expert advice to the MSRC.

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TS 6.1 10 e.

Meeting Frequency The MSRC shall meet at least once per calendar quarter.

h f.

Quorum The minimum quorum of the MSRC necessary for the performance of the MSRC review and audit functions of these Technical Specifications shall consist of the Chairman or his designated alternate and at Itast 50% of the MSRC members including alternates.

No more than a minority of the quorum shall have line responsibility for operation of the unit.

g.

Review

-TheJ 'SRC shall be responsible for the review of:

1.

.The safety evaluations for 1) changes to procedures, equipment-or systems and' 2)- tests or experiments completed under the = provision of Section-.50.59,10 CFR, to verify that: such actions did not constitute an unreviewed safety. question..

2.

Proposed changesq toy procedures, equipment or systems y

which; involve an unreviewed: safety question as defined y

in Section 50.59,10 CFR.

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3.,

Proposed tests or experiments which : involve an unroviewed safety question. as-defined in 'Section 50.59, 10 CFR.

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ProposedL changes: to Technical Specifications ; or ~.the 1;%

Operating Licenses. -

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-Amendment Nos. 146-and 142, Sl 4

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6 TS 6.1 11 5.

Violations of codes, regulations,

orders, Technical Specifications, license requirements, or of internal procedures-or instructions having nuclear safety significance.

6.

Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear safety.

7.

Events requiring written notification to the Commission.

8.

All. reccgnized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could affect nuclear safety.

9.

Reports and meeting minutes of t_he SNSOC.

h.

Audits Audits of facility activities shall be. performed under the cognizance of the MSRC. These audits shall^er. compass:

1.

The conformance of, facility operation.to provisions 3

containe'd within ' the. Technical : Specifications-and applicable license conditions at ;least once per 12 months.

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' 2.

The performance, training. and. qualifications of the j

6 entire facilityistaff at least once per 12 months, i

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'3.

The' results :of. actions taken Lto1 correct deficiencies 4

' occurring in. facility equipment, structures, systems 'or l

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. method i off operation - thatiaffect nuclear safetyg at ;l' east

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1 onc'e per 6 months.

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.I, Araendment Nos.146 I rand 142,<

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TS 6.1 12 4-4.

The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix "B",10 CFR 50, at least once per 24 i

months.

5.

The Emergency Plan and implementing procedures at least once per 12 months.

i 6.

The Security Plan and implementing procedures at least once per 12 months.

l 7.

Any other area of facility operation considered 1

appropriate by the MSRC or the Vice President - Nuclear Operations.

L 8.

The Fire Protection Program and implementing procedures at least once per 24 months.

9.

An independent fire protection and loss prevention inspection and audit shall be performed -annually utilizing either qualified offsite licensee personnel or an outside_ fire protection firm.

1 10.

An inspection ~ and audit-of' the fire protection-and ~ loss p

prevention program shall be performed. by-an outside

._ qualified fire consultant at intervals no greater. than-3 L

years.

11.

The radiological environmental monitoring' program.at

-

• least.once per 12 months.

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12. -

The Offsite Dose Calculation Manual and implementing proceduresrat _least once per 12 months.-

.t-13.

Th'e : Process-Control Program and implementing i

procedures forLprocessing and packaging of. radioactive a

waste at _least once per 12 months.

Amendment Nos.146 and 142, I

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TS 6.1 13 l.

Authority The MSRC shall report to and advise the Senior Vice President Nuclear on those areas of r 9sponsibility specified in Sections 6.1.c.2.g and 6.1.c.2.h.

j Records Records of MSRC activities shall be prepared, approved and distributed as indicated below:

1.

Minutes of each MSRC meeting shall be prepared, r

approved and forwarded to the Senior Vice President -

Nuclear within.14 days of each meeting.

2.

Reports ' of. reviews with safety significant findings

I en. compassed by Se'ction 6.1.c.2.g ' above, shall be t

prepared,. approved and forwarded to the Senior-Vice President'- Nuclear within 14 days following completion of ' the review.

3.

Audit reports encompassed by Section 6,1.c.2.h' above, shall be forwarded to the Senior Vice President Nuclear and to the management positions : responsible.for the areas audited within -30 days after ' completion of: the

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audit ' by the - auditing--_ organization.

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TS 6.21 3-.

6.2 GENERAL NOTIFICATION AND REPORTING REQUIREMENTS Soecification A.

The following actions shall be taken for Reportable Events:

1, A report shall be submitted pursuant to the requirements of Section 50.73 to 10 CFR, and l

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2.

Each Reportable Event shall be reviewed by the SNSOC.

The' Vice President - Nuclear Operations and the MSRC shall be notified of the results of this review.

B.

Immediate notifications shall be made in accordance with Section 50.72 to 10 CFR.

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TS 6.3-1 6.3 ACTION TO BE TAKEN IF A SAFETY LIMIT IS EXCEEDED Soecification 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 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

2.

The Safety Limit violation shall be reported to the' Commission, the Vice President - Nuclear Operations, and the MSRC within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, i

3.

A Safety Limit Violation Report shall be prepared.- The

. report shall be reviewed by the SNSOC.

This report shall i

describe (1) applicable circumstances preceding the -

violation, (2) effects of - the violation upon facility l_

components, systems or structures, and (3) corrective' action taken to prevent recurrence.

4.

.The'. Safety Limit - Violation Report shall be submitted _to-

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the. Commission, the Vice President - Nuclear Operations, and the MSRC-within 14 days of the violation.

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