Text

Amends 30 & 11 to Licenses NPF-4 & NPF-7,respectively, Revising Administrative Controls Reflecting Corporate & Plant Reorganizations,Adding Assistant Station Manager & Establishing Safety Evaluation & Control Group
	ML20004C392
Person / Time
Site:	North Anna
Issue date:	05/22/1981
From:	Clark R; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20004C393	List: ML20004C392; ML20004C394; ML20004C395;
References
	NUDOCS 8106030473
	Download: ML20004C392 (63)
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- UNITED STATES

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' NUCLEAR REGULATORY COMMISSION s

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L VIRGINIA ELECTRIC AND-POWER COMPANY DOCKET-NO. 50-338 t

NORTH ANNA POWER' STATION, UNIT NO. 1-

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AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 30 License No. NPF-4

-1.

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

A.-

The applications for amendments by Virginia Electric and Power Company (the licensee) dat]d A'y 30, 1980, August 28, 1980 and October 15, 1980 as -supplemnted -by letters dated August 1, 1980 and February 23, 1981, comply with the standards and..

~-l 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 pubite, and (til that such activities will be conducted in-compliance with the Commission's regu ations; 4

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.

1 B106030 tk7 m...

'l 2-2' Accordingly, the license'is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.D.(2) of Facility Operating License No. NPF-4 is hereby amended to read as follows:

-(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 30, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. -This license amendment is effective May 29,1981.

FOR THE NUCLEAR REGULATORY COMMISSION M

L-Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: May 22, 1981 4

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e ATTACHMENT.T0 LICENSE AMENDMENT AMENDMENT NO. 30 TO FACILITY OPERATIN7 LICE' 'iE NO. NPF-4 1

DOCKET NO. 50-338-

<l Replace _the following:pages of the_ Appendix "A" Technica1' Specifications with the enclosed-pages as indicated. The revised pages are' identified by Amendment number and_contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain

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document completeness.

Pages XVIII XIX-6-1 6-la (added) 6-2 6-3 6-4a 6-5 6-6 6-7 6-8 6-9 6-10 6-11 6-12 6-21 4

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~ PAGE 5.1 iSITE Exclusion: Area................................................

5-1 Low-Population Zone..........................................

.5-11

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5.2' CONTAINf1ENT Configuration................................................

' 5 : Design Pressure and Temperature..............................

5-4 5.3 REACTOR CORE Fuel Assemblies..............................................

5-4

Cor. col Rod Assemblies.......................................

' 5 -4 5.4 REACTOR COOLANT SYSTEM Design Pressure and Temperature..............................

5-4 Vo1ume.......................................................

5-5 E.5. METEOROLOGICAL TOWE R LOCAT

0N................................- 5 5.6'-FUEL STORAGE Criticality.................................................

5-5 Drain;ge....................................................

5-6 C a p a c i ty....................................................

5-6 5.7 COMPONENT CYCLE OR TRANSIENT LIMIT..........................

5-6 NORTH ANNA-UNIT'1 XVII i

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INDEX ADMINISTRATIVE CONTROLS' SECTION PAGE 6.-1 RESPONSIBILITY................................................

6-1 6.2 -ORGANIZATION

'0ffsite.........................................................

6-1 n

Facility Staff..................................................

6-It Safety Engineering Staff.....................................

6-la.

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Shift Technical Advisor.........

6-la-6.3 FACILITY STAFF QUALIFICATIONS................................

6 6.' 4 TRAINING.....................................................

6-5 6.5 REVIEW AND AUDIT 6.5.1 STATION NUCLEAR SAFETY AND OPERATING COMMITTEE ~(SNSOC)

Function........................................................

6-5 Composition.....................................................

6-5 Alternates......................................................

6-5 Meeting. Frequency.....................................

6-6 Quorum..........................................................

6-6 Responsibilities................................................

6-6 Authority.......................................................

C' 7 Records.........................................................

6-7 6.5.2 SAFETY EVALUATION AND CONTROL (SEC)

Function........................................................

6-7 Composition.....................................................

6-8

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NORTH ANNA-UNIT 1 XVIII Amendment No. 30 e

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INDEX.

ADMINISTRATIVE CONTROLS t

SECTION PAGE Consultants..................................................... 8 Meeting Frequency...............................................

6-8_-

1 Review..........................................................

6-8 Authority.......................................................

6 Records.........................................................

6-9 6.5.3 QUALITY ASSURANCE DEPARTMENT Function........................................................

6-10 Authority.......................................................

6-10 Records.........................................................

6-11 6.6 REPORTABLE OCCURRENCE ACTI0N.................................

6-12 6.7 SAFETY LIMIT VIOLATION.......................................

6-12 6.8 PROCEDURES...................................................

6-13 6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REPORTS AND REPORTABLE OCCURRENCES.................

6-13 6.9.2 SPECIAL REP 0RTS............................................

6-18 6.10 RECORD RETENTION............................................

6-20 6.11 RADIATION PROTECTION PR0 GRAM................................

6-21 6.12 HIGH RADIATION AREA.........................................

6-22 6.13 ENVIRONMENTAL 00ALIFICATION.................................

6-23

- 1, NORTH ANNA-UNIT 1 XIX Amendment No. 30

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6.0 ADMINISTRATIVE CONTROLS 6.1-RESPONSIBILITY ~

6.1.1.LThe Station Manager shall be responsible for overall facility operation.

In his absence, the Assistant Station Manager shall be responsible for overall facility;operatica.

During the absence of both, the Station Manager shall' delegate in writing;the succession to this responsibility.

6.1. 2 The Shift' Supervisor (or during his absence' from the Control Room, a designated individual) shall be responsible for the Control Room command function and.shall be the only individual that may-direct the licensed; activites of. licensed operators.

A management directive to this effect, signed by the Executive Vice President-Power, snall be reissued to all rtation personnel on an annual basis.

6.2 ORGANIZATION OFFSITE.

6.2.1 The offsite organization for facility management and technical support shall be as shown on Figure 6.2-1.

FACILITY STAFF 6.2.2 The Facility organization shall be as shown'on Figure 6.2-2 and:

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a.

Each on duty shift shall be composed of at least the minimum

-hift crew composition shown in Table 6.2-1.

b.

At least one licensed Reactor Operator shall be in the control room when fuel is in the reactor.

In addition, while the unit is in MODES., 2, 3 or 4, at least one licensed Senior Reactor Operator shall be in the Control Room.

c.

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

d.

ALL CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Reector Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.

.e.

A Fire Bri<,ade of at least 5 members shall be maintained onsite at all tim :s#.

The Fire Brigade shall not include the minimum j

shift crew shown in Table 6.2-1 or any personnel recairec for other essential functicas during a fire emergency.

I#Tne health physics tecnnician and Fire Brigage composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months i

in order to accommodate unexpected abunce provided immediate action is l

taken to fill the required positions.

NORTH ANNA-UNIT 1 6-1 Amendment No. 3, 16, 79, 30 t

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ADMINISTRATIVE CONTROLS

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d.2.3 SAFETY ENGINEERING STAFF (SES)

UNCTION 6.2.3.1~- The SES shall: function to examine plant operating;charac+cristics,.

NRCEissuances, industr/ advisories, Licensee Event Reports, and other sources

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which may indicate areas for. improving plant safety.

COMPOSITION

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6.2.3.2 The SES shall.be' composed of at'least five dedicated,' full-time engineers located onsite.

RESPONSIBILITIES 6.2.3.3 The SES shall be responsible for maintaining surveillance of plant

' ctivities to provide independent verification

that these activities are -

a performed correctly and that human errors are reduced as much as. practical.

l AUTHORITY 6.2.3.4 The SES shall.make detailed recommendations for revised procedures, aquipment modifications, or other means of improving plant safety to the LStation Manager..and the Director-Safety Evaluation and Control.

,6.2.4 SHIFT TECHNICAL ADVISOR i

6.2.4.1 The Shift Technical Advisor shall serve in an advisory capacity to Shift Supervisor on matters pertaining to the engin:aring aspects of assuring safe operation of the unit.

6.2.4.2 -The Shift-Technical Advisor shall dissemi.1 ate relevant operational experience identified by the SES.

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Not responsible for sign-off function.

i NORTH ANNA-UNIT 1-6-la Amendment No. 30 l

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'6-2 Amendment No. 3, 77,.77, 30

Figure 6.2-2 Facility Organization - North Anna '- Units l' and 2 -

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MINIMUM SHIFT-CREW COMPOSITION' WITH UNIT 2 IN MODE 5 OR 6 OR DE-FUELED POSI TION NUMBER'0F INDIVIDUALS REQUIRED TO FILL POSITION MODES 1, 2, 3, & 4 M00ES-5 & 6 a-a SS'

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bj One of the two_ required individuals may fill the same posi. ion on Unit 2.

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I TABLE 6.2-1 (Continued)-

j SS - Shift Supervisor with a Senior _ Reactor Operators License on' unit 1.

SRO -; Individual with'a Senior Reactor Operators License on Unit 1.

RO - Individual with a Reactor Operators License on Unit 1.

-A0 - Auxiliary Operator STA -: Shift Technical Advisor Except for the Shift Supervisor, the Shift Crew Composition may be one less sthan the minimum requirements o-Table 6.2-1 for a period of time not to exceed.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in orcer to accommodate unexpected absence of on-duty shift crew members providec immediate action-is taken to. restore the Shift. Crew Composition to within the minimum requirements:of Table 6.2-1.

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

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unit is in MODE 1, 2, 3'or 4, an individual'(other than the Shift Technical

- Advisor) with a valid SRO license snall be designated to assume the Control

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Room command function. During any absence of the Shift-Supervisor from the Control Room while the unit is in MODE 5 or 6, an individual with a valid R0 license (other than the Shift Technical Advisor) shall be designated to assume the Control Room :ommand function.

Licensed operators shall:*

1.

Not work more than 12 haurs straight, 2.

Not work more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in any 48-hour period, 3.

Not work more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 7-day period, 4.

Not work more than 14 consecutive-days without ha'/ing 2 consecutive days off.

0eviation from these requirements may be authorized by tne Station Manager in accordance with established procedures and with documentation of the cause.

-Overtime limits do not 'eclude the shift turnover time.

NORTH ANNA-UNIT 1 6-4a Amendment No. 79, 30 o -

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ADMINISTRATIVE CONTRLS 6.3 FACILITY STAFF OUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1 ---1971 for comparable positions and the.

supplemental' requirements spacified in.the March 28, 1980 NRC letter to all licensees, except for (1) the Supervisor. -- Health Physics who

'shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975 and (2) the Shift Technical Advisor who shall have a bachelor's degree or equivalent in a scientific or engineering discip-line.with specific training in plant design, and response and analysis of the plant for transients and accidents.

6.4 TRAINING 6.4.1 The Station Manager is responsible 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 supple-mental requirements specified in the March 28, 1980 NRC letter to eil licensees,

,and shall include familiarization w'..a relavt t industry operational experience

': identified by the SES.

6.5 REVIEW AND AUDIT 6.5.1 STATION NUCLEAR SAFETY AND OPERAT..dG COMMITTEE (SNSOC)

FUNCTION 6.5.1.1 The SNSOC sha'l function to advise.the Station Manager on all~ matters related to nuclear safety.

COMPOSITION

6. 5.1. 2 The SNSOC shall be compos,d of the :

Chairman:

Station Manacer Vice Chairman:

Assistant Station Manager l

Member:

Superintendent-0perations Member:

Superintendent-Maintenance Member:

Superintendent-Tech:.: cal Services l

Member:

Supervisor-Health Physics l

ALTERNATES I

6.5.1.3 All alternate members shall be appointed in writing by the SNSOC Chairman to serve on a temporary basis; however, no more tnan one

alternate shall participate as a voting member in SNSOC activities at l

.any one time.

l NORTH ANNA-UNIT L 6-5 Amendment No. 3, 77, 77, 30

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l MEETING FREQUENCY

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

. convened by the SNSOC Chairman-or his designated alternate.-

QOORUM 6.5.1.5 ALquorumof.theSNSOCconsistsoftheChairmanorVice-Chairman and two members including alternates.

-RE:?ONSIBILITIES 6.5.1.6 The SNSOC shall be responsible for:

a.

- Review of 1) all procedures required by Specification 6.8.1 and.

changes thereto, 2) any other' proposed procedures or changes

-thereto as determined by the Station Manager to affect nuclear

safety, b.

Review of all proposed tests and experiments that affect l

nuclear safety.

c.

. Review of all proposed changes to Appendix "A" Technical

' Specifications.

d.

Review of all' proposed. changes or modifications to plant systems or equipment that affect nuclear safety, e.

Investigation of all violations of the Technical Specifications including the preparation and forwarding o' reports covering evaluation and recommendations to prevent recurrence to the-Manager-Nuclear Operations and Maintenance and the Director-Safety i

Evaluation and Conorol.

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f.

Review of events requiring 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months written notificat:on to the Commission.

g.

Review of facility operations to detect potential nuclear i

safety hazards.

h.

Per-rmance of special reviews, investigations or analyses and reports thereon as requested by the Chairman of the Station Nuclear Safety and Operating Committee.

i.

Review of the Plant Security Plan and implementing procedures l

and shall submit recommended changes to the Chairman of the l

Station Nuclear Safety and Operating Committee.

j.

Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the Chairman of the Station, Nuclear Safety and Operating Committee.

NORTH ANNA-UNIT 1 6-6 Amendment No. 17,30 f

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ADMINISTRATIVE CONTROLS AUTHORITY

.. -3;521.7 - The SNSOC shalli 4-

- a; Recommer.d to the Station Manager written approval-or disapproval of items considered under 6.5.1.6(r) through-(d) above.

b.

Render determinations-in writing with regard to whether or not' each item considered under 6.5.1.6(a) through (e) above constitutes.an unreviewed safety question.

c.

~ Provide written notification within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to Manager-Nuclear

' Operations and Maintenance and the Director-Safety Evaluation and-

' Control of disagreement between the SNSOC and the Station Manager;

_ however,.the Station Manager 'shall have responsibility for-resolu-tion of such disagreements pursuant to 6.1.1_above.

RECORDS 6.5.1.8: The.SNSOC shall maintain written' minutes ofLeach meeting and-copies shall be provided to the Manager-Nuclear Operations' and Maintenance and the Director-Safety._ Evaluation and Control.

6 5.2 SAFETY EVALUATION AND CONTROL (SEC)

FUCTION~

'6.5.2.1 SEC shall function to provide independent review of~ designated-

. activities in the areas of:

a.

Nuclear power plant operations b.

Nuclear engineering

' c.

Chemistry and radiochemistry d.

Metallurgy e.

Instrumentation and control

- f.

. Radiological safety g.

Muhanical and electrical engineering h.

Administrative controls and quality assurance practices l

i.

.0ther appropriate fields associated with the unique char-l acteristics of the nuclear power plant I

NORTH ANNA UNIT 1 6-7 Amendment No. 77,30

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ADMINISTRATIVE CONTROLS

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COMPOSITION.

6.5'.2.2 The SEC staff shall be composed of the Director-Safety Evaluation and Control and a minimum of three individuals who are qualified as staff specialists..Each SEC staff specialist 'shall have an academic degree in' an engineering or physical. science' field and, in addition, shall have a minimum of five years technical experience in one or more areas given in Specification.

6.5.2.1.

The.se staff specialists shall not be directly involved'in the licensing function.

CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the Director-Safety Evaluation and. Control to provide expert advice to the SEC.

MEETING FRE0VENCY 6.5.'2.5 The SEC staff shall meet at least once per calendar month for tFe l..

purpose of fostering interaction of reviews regarding safety-related. opera--

tional activities.

REVIEW 6.5.2.7 The following subjects shall be reviewed by SEC:

. l a.

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 without prior URC approval under the provisions of 10 CFR 50.59(a)(1).

This review is to verify that such changes, tests or experiments did not involve a change in l

the technical specifications or an unreviewed safety question as defined in 10 CFR 50.59(a)(2) and is accomplished by review of minutos of the Station Nuclear Safety and Operating Committee and the desigt l

change program.

l b.

Proposed changes in procedures, croposed changes in the station, or proposed tests or experiments, any of which may involve a change in i

the technical specifications or an unreviewed safety question as defined in 10 CFR 50.59(a)(2).

Matters of this kind shall be referred Safety and Operating Committee following its review prior to implementa-l to the Director-Safety Evaluation and Control Ly the Station Nuclear 1

l i

tion.

c.

Changes in the technical specifications 'r license amendments relating to nuclear safety prior to i.mplementatica except in those cases where the change is identical to 6 previously reviewed proposed change.

! NORTH ANNA-UNIT 1 6-8 Amendment No. II, 77, 30 I

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-s ADMINISTRATIVE CONTROLS d.

. Violations _and report 3ble occurrences such as:

1.

Violations'of applicable codes,'re'gulatitas, orders, Technical

~ Specifications, license.re :uirements or. internal. p:acedures or instructions having safety significance; 2.

Significant operating abnormalities or deviations from normal:

or expected performance of station safety-related structures, systems,-or components; and 3.

Reportable occurrences as defined in the station Technical Specification 6.9.1.8.

l Review of events covered under this paragraph shall include the results of. any investigations made and recommendations resulting-from such investigations to prevent'or reduce the probability of recurrence of the event.

e.

The Quality Assurance Department audit program at least once per i

12 months and audit reports.

I f.

Any othe-matter involving safe operation of the nuclear power stations which is referred to the Director-Safety Evaluation and Control oy the Station Nuclear Safety and Operating Committee.

g.

Reports and meeting minutes of the Station Nuclear Safety and l

Operating Committee.

AUTHORITY 6.5.2.9 'The Director-Safety Evaluation and Control shall report to and advise the Manager-Nuclear Technical Services, who shall advise the Vice President-Nuclear Operations on those areas of responsibility specified in Section 6.5.2.7.,

RECORDS 6.5.2.10 Records of SEC activities required by Section 6.5.2.7 shall be prepared and maintained in the SEC files and a summary shall be disseminated as indicated below each calendar montn.

1.

Vice President-Nuclear Ogarations 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 lNiTHANNA-UNIT 1 6-9 Amendment No. 30

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' ADMINISTRATIVE CONTROLS-6.5.3 QUALITY ASSURANCE DEPARTMENT FUNCTION

, s.5.3.1 The_ Quality Assurance Department shall function to'-audit station-activities.

These audits shall encompass:

a.-

The conformance of facility operation to provisions contained within.

the Technical. Specifications and applicable license conditions at least once per 12 months.

b.

The performance, training and qualifications of the' entire facility staff at least once per 12 months.

c.

The results of actions taken.to correct deficiencies-occurring in r

faci.11ty. equipment, structures, systems or mecnod of operation that e

affect nuclear safety at least once per 6 months.

. d.

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 months.

e.

The Station Emergency Plan and implementing procedures at least once per 24 months.

f.

The Station Security Plan and implementing procedures at least once '

per 24 months.

t l'

g.

Any other area of facil.ty operation considered appropriate by the Executive Manager-Quality Assurance or the Senior Vice President-Power Operations.

l h.

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

i.

An independent fire protection and loss prevention program inspection l

and audit shall be performed at least once per 12 months utilizing either qualified offsite licensee personnel or an outside fire pro-i tection firm.

i i

j.

An insp,ection and audit of the fire protection and loss prevention program shall be performed by a qualified outside fire consultant at least once per 36 months.

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AUTHORITY 6.5.3.2 The Quality Assurance Department shall report to and advise the f

Executive Manager-Quality Assurance, who shall advise the Senior Vice

[

l President-Power Operations on those areas of responsibility specified in l

Section 6.5.3.1.

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NCRTH ANNA-UNIT.1 6-10 Amendment No. M, 30 f

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ADMINIST.eATIVE CONTROLS t

RECORDS 6.5.3.3 Records.of the Quality' Assurance Department audits'shall be prepared 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

'7.

.Suoervisor of area audited 8.

Nuclear Power Station Resident Quality Control Engineer

! NORTH ANN;-UNIT 1 6-11 Amendment No. 3, 5. 77. 30 L

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ADMINISTRATIVE CONTROLS-6.6 REPORTABLE OCCURRENCE ACTION 6.6.11The;following actioris shall be taken for R2 PORTABLE OCCURRENCES:

a.

The Commission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.9.

b.

. Each REPORTABLE OCCURRENCE requiring 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months notification to the Commission shall be revi.ewed by the SNSOC and submitt.?1 to the Director-Safety Evaluation and Control ~and the tianager,1uclear

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Operations and Maintenance.

I 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall.be taken in the event a Safety Limit is violated:

-a.

The facility shall be'placed in at least HOT STANDBY within

.one t.our.

b.

The Safety Limit violation shall be reported to the Commission, the Manager-Nuclear 0nerations and Maintenance and to the Director-Safety Evaluation and Control within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

c.

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.

d.

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.

I i

1.

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h NORTH ANNA-UNIT 1 6-12.

Amendment No. 3, 5, 77, 30

o 4

ADMINISTRATIVE CONTROLS a.

Records and arawing changes reflecting facility design modifi ~

cations made to systems and equipment described in the Final Safety Analysis Report, b..

Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.

c.

Records of facility radiation and contamination surveys.

d.

Records of. radiation exposure for all individuals entering radiation control areas, e.

Records ofl gaseous and-liquid radioactive, material released to the environs.

f.

Records of transient operational cycles for those facility components identified in Table 5.9-1.

g.

Records of reactor tests and experiments.

h.

Records of training and qualification fcr current members of the plant staff.

i.

Records'of in-service inspections performed pursuant to these Technical Specifications, j.

Records of Quality Assurance activities required by the Q*

Manual.

k.

Records of reviews performed for changes made to procedures or equipment or reviews of. tests and experiments pursuant to 16 CFR 50.59.

1.

Records of meetings of the SNSOC.

m.

Records of meetings of the System Nuclear Safety and Operating Committee to issuance of Amendment No.

n.

Records of secondary water sampling and water quality.

l o.

Records of Environmental Qualification which are covered under the provisions of paragraph 6.13, 6.11 RAutaTION PROTECTION PROGRAM 1

Procedures for personnel radiation protection shall be prepared con-sistent with the requirements of 10 CFR~Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radia--

' tion exposure.

NORTH ANNA-UNIT 1 6-21 Ofddt ditdd Ottd5df 24, 1980 Amendment No. 30 j

AD!'INISTRATIVE CONTROLS 6.12 HIGH RADIATION AREA 6.12.1-In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiation is greater ~than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall.be controlled by requiring issuance of a Radiation Work Permit.* Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a.

A radiation monitoring device which continuously indicates the radiation dose rate in the area, b.

A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made knowledgeable of them, c.

An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device.

This individual shall be responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified.

by the facility Health Physicist in the Radiation Work Permit.

6.12.2 The requirements of 6.12.1, above, shall also apply to each high radiation area in which the intensity of radiation is greater than 1000 mrem /hr.

In addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administrative control of the Shift Supervisor on duty and/or the Plant Health Physicist, i.

l f

Health Physics personnel shall be exempt from the RWP issuance require-ment during the performance of their assigned radiation protection l

duties, provided they comply with approved radiation protection j

proc 2dures for entry into high radiation areas.

1 NORTH ANNA - UNIT 1 6-22 Amendment No.16 4

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' ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 30 TO FACILITY OPERATING LICENSE NO. NPF-4 DOCKET NO. 50-338' t

Replace the following pages of the Appendix "B" Technical Specifications-with the enclosed pages as indicated. - The revised pages are identified by Amendment number and contain vertical lines indicating the area of-change.

-Pages I-i 1 I-5-1 I-5-2 I-5-3 I-5-4 I-5-5 4

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t TABLE OF CONTENTS E*L* -

1.0 DEFINITIONS......................................................

1-1 2.0 LIMITING CONDITIONS FOR OPERATION................................

2-1 2.1' Non-Radiological............................................

2-1 2.2 Radioactive Effluents.......................................

2-1 2.2.1 Specifications-for Liquid Waste Effluents.........

22 2.2.2 Specifications for Liquid Waste Sampling and Monitoring..................................

2-3 2.2.3 Specifications for Gaseous Waste Effluents........

2-7 2.2.4 Specifications for Gaseous Waste Sampling and Monitoring.................................. 13 2.2.5 Specifications for Solid Waste Handling and Disposal....................................

2-1*

3.0 ENVIRONMENTAL SURVEILLANCE.......................................

3-1 3.1 Non-radiological Survei11ance...............................

3-1 3.1.1 Abiotic - Aquatic.................................

3-1 3.1.2 Biotic Aquatic...................................

3-1 3.1.3 Abiotic - Terrestrial.............................

3-1 3.1.4 Onsite Meteorology Monitoring.....................

3-1 3.2 Radiological Environmental Monitoring....................... 2 4.0 SPECIAL. SURVEILLANCE AND STUDY ACTIVITIES........................

4-1 5.0 ADMINISTRATIVE CONTR0LS..........................................

5-1 5.1 Responsibility..............................................

5-1 5.2 Organization................................................

5-1 5.3 Review and Audit............................................

5-1 5.3.1 Station Nuclear Safety and Operating Committee (SNS0C).........................................

5-1 7

.3.1.1 Function................................

5-1 5.3.1.2 Responsibility..........................

5-1 5.3.1.3 Authority.....................

5-3 5.3.1.4 Records.................................

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, TABLE OF CONTENTS (Cont'd) 3, Pagg 5.3.2 Quality Assurance Department......................

5-4 l-5.3.2.1 Function................................

5-4 5.3.2.2 Audits..................................

5-4 5.3.2.3 Records.................................

5-4 5.3.3 Safety Evaluation and Control (SEC)...............

5-4

.l 5.3.3.1 Function................................

5-4 5.3.3.2 Review..................................

5-4 5.3.3.3 Responsibility..........................

5-5 5.3.3.4 Authority...............................

5-5 5.3.3.5 Records.................................

5-5 5.4 State and Federal Permits and Certificates..................

5-5 5.5' Procedures..................................................

5-5 5.5.1 Written Procedures................................

5-5 5.5.2 Operating Procedures..............................

5-5 5.5.3 Procedures for Environmental Surveillance -

Radiological..............

5-6 5.5.4 Procedures for Environmental Surveillance -

Nonradiologica1.................................

5-6 5.5.5 Quality Assurance of Program Results..............

5-6 5.5.6 Changes in Procedures, Station Design or Operation.......................................

5-6 5.5.7 Consistency with Initially Approved Programs......

5-7 5.6 Station Reporting Requirements..............................

5-7 5.6.1 Routine Reports...................................

5-7 5.6.1.1 Annual Environmental Operating Report...

5-7 5.6.1.2 Radioactive Effluent Release Report.....

5-8 5.6.2 Nonroutine Reports................................

5-9 5.6.2.1 Nontc" tine Non-Radiological Environmental Operating ?.:rort......................

5-9 5.6.2.2 Nonroutine Radiological Environmental Opera ting Reports.....................

5-10 l

5.6.3 Changes in Environmental Technical Specifications.

5-11 5.6.4 Changes in Permits and Certifications.............

5-11 5.7 Records Retention...........................................

5-11 I-ii Amendment No. 30

1

~5.0

' ADMINISTRATIVE CONTROLS Administrative controls below apply.to Appendix B Part I only.

5.1 Responsibility The responsibility for implementing the Environmental Techneial' Specifications is assigned to the Manager-Nuclear Operations and Maintenance.at the corporate -

level and to the Station Manager at the station level. The Superintendent -

Operations shall be responsible for ensuring that the station is operated.in accordance with the Limiting Conditions of Operation. The Station Supervisor --

Health Physics shall be responsible for the radiological environmental surveillance requirements. The Executive Manager of Environmental Services l

shall be responsible for providing services' which will fulfill the non-radiological environmental surveillance requirements.

5.2 Organization-The relationship'between the Nuclear Operations Department and the Environmental Services Department is shown in Figure 5.2-1.

5.3.

Review and Audit 5.3.1 Station Nuclear Safety and Operating Committee-(SNSOC) 5.3.1.1 Function The SNSOC, as described in Section 6.5.1 of Appendix A of this license, shall function to advise the Station Manager on matters related to the environmental impact of the station. With the SNSOC is exercising its responsib.lity for non-radiological aspects of the ETS, the Station Biologist or his alternate shall be consulted.

5.3.1.2 Responsibility The SNSOC shall be responsible for:

a.

Coordination of the Environmental Technical Specifications with the Safety Technical Specifications (Appendix A) to avoid con-flicts and maintain consistency.

b.

Review of changes to the Environmental Technical Specifications and the evaluation of the environe-tal impact of the change.

I-5-1 Amendment No. 30

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~ Review of proposed' written procedures required by Section 5.5.2 and 5.5.3 below and changes thereto, which affect the environmental impact of the station.

d.

Review of proposed changes to station systems to. determine the-environmental impact of the changes.

e.

Investigation of all reported. instances of violation of the (Environmental Technical Specifications; and where the investiga-

tion indicates, evaluation and formulation of recommendatiens to prevent recurrence.

f.

Review af environmental monitoring programs to detect potentfil or existing significant adverse environmental impacts that bave not been evaluated, or that are significantly greater.than :5at evaluated by the Commission.

5.3.1.3 Authority The SNSOC shall:

a.

Review the environmental evaluation of all changes described in:

Section 5.3.1.2 a, b and c, above. When the evaluation indicates.

that such activitiy may result in a significant adverse environ-mental impact that was not evaluated, or that is significantly greater than that evaluated by the Commission, the SNSOC shall ensure that.a written evaluation of such activities is provided to and prior approval is obtained from the Director of Nuclear Reactor Regulation for the activities.

b.

If the INSOC. determines thtt unexpected harmful effects or evidence of irreversible damage are occurring as a result of operation of the station, the SNSOC shall ensure that an acceptable analyris of the problem and a plan of action to eliminate or significently reduce the harmful effects or damage is submitted to the Commission for review and approval.

c.

Review written reports prepared as a result of investigations and reviews conducted under 5.3.1.2 a, e and f.

5.3.1.4 Records l

lThe SNSOC shall maintain written minutes of each meeting and copies l

shall be provided to the Director-Safety Evaluation and Control.

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t I-5-3 Amendment No. 30

- 5.3.2 Quality Assurance Department Function

.5.3.2.1 The Quality Assurance Department shall' perform indepenaent' audits of

._the implementation of the Environmental Technical Specifications.

-5.3.2.2

? Audits The=following' audits shall be completed:

a '. -

The conformance of facility operation to' provisions contained

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within these Environmental. Technical Specifications and applica-ble license conditions at least once per 12 months.

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l b.

The performance, training and qualifications of the facility staff involved in ensuring and monitoring compliance.with these Environmental Technical Specifications at least once per 12 months.

c.

The results of action taken to correct deficiencies occurring in i

facility equipment, structures,' systems or method of operatio.n j

that affect the environmental impact of the station at least once i

per 12 months.

5.3.2.3 Records

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Provide a written report of the results of the audits required by 5.3.2.2 above to the SNSOC, the Director-Safety Evaluation and Control, and the Station Manager.

5.3.3 Safety Evaluatio and control (SEC) 5.3.3.1 Function SEC, as described in Section 6.5.2 of Appendix A of this license,

~l shall function to provide independent review of designated activities related to the environaental imp >tt of the station.

-5.3.3.2 Review SEC shall review and, where necessary, comment on the results of the reviews conducted by the SNSOC aad the independent audits conducted by the Ouality Assurance Department.

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5 3.3.3' Responsibility SEC has.the responsibility for ensuring, through appropriate reviews, that the station is orarated in accordance with the requirements of this license and applicable NRC~ regulations.

5.3.3.4~

Authority-The Director-Safety Evaluation and Control shall reportLto and advise the Manager-Nuclear Technical Services, who shall advise.the Vice President-Nuclear Operations ou those areas relating to the-environmen-

~

tal impact of the station.

.5.3.3.5 Records The records of SEC activities relating to the environmental impact of the station 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.

5.4 State and Federal Permits and Certificates None 5.5 Procedures 5.5.1 Written Procedures Detailed written procedures, including applicable checklists and instructions, shall be prepared and followed for all activities involved in carrying out the Environmental Technical Specifications as defined in See: ion 5.5.2, 5.5.3, and 5.5.4, below.

Procedures shall include sampling, data recording and storage, instrument calibration, measure-ments and analyses,'and actions to be taken when limits are approached or exceeded. Testing frequency of any alarm shall be included. These frequencies shall be determined from experience with similar instru-ments in similar environments and from manufecturer's technical manuals.

5.5.2 Operating Procedures Plant standard operating procedures shall include provisions, in addition to the procedures specified in Section 5.5.1, to ensure that all plant systems and components are operated in compliance with the Limiting Conditions of Operations established as part of the Environ-mental Technical Specifications.

1-5-5 Amtidment No. 30

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VIRGINIA ELECTRIC AND POWER COMPANY 00CKET NO. 50-339 NORTH ANNA POWER STATION, UNIT NO. 2 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No.11 License No. NPF-7 l'

1.

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

A.

The applications for amendments by Virginia Electric and Power Company (the licensee) dated July 30, 1980, August 28,1980 and October 15, 1980 as supplemented by' letters dated August 1, 1980 and February 23, 1981, comp'.y with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rulu and regulations set forth in

'10 CFR Chapter I; B.- The facility will operate in confonnity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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; O.

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 a'.'l applicable requirements have been satfsfied.

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i 2.. Accordingly, the Itcense.is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment,' and paragraph 2.C.(2) of Facility Operating' License No. NPF-7 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.11, are hereby incorporate.d in the license. The licensee shall operate.the faci *ity in accordance with the Technical.

Specifications.

3.

This license amendment is effective May 29, 1981.

FOR THE~ NUCLEAR REGULATORY COMMISSION Ew Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: May 22, 1981 I

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ATTACHMENT TO LICENSE AMENDMENT I-AMENDMENT NO. 11 TO FACILITY OPERATING LICENSE NO. NPF-7 00CKET NO. 50-339, Replace-the following pages of the Appendix "A" Technical Specificatior.s with the enclosed pages as. indicated. The revised pages' are identified by Amendment number and contain vertical if nes indicating the area of change. The corresponding overleaf pages are also provided to maintain document comple' 2 ness.

Pages XVI XVII 6-1 6-la 6-2 6-3 6-6 7 6-8 6-9 6-10 6-11 6-12 6-13 6-20 i

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VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-339 NORTH ANNA POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. I1 License No. NPF-7

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

A.

The applications for amendments by Virginia Electric and Power Company (the licens'ee) dated July 30, 1980, August 28, 1980 and October 15, 1980 as supplemented by letters dated August 1, 1980 and February 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 confomity 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 sucli activities will be conducted in conpliance 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 amebded by changes to the Technical

- Specifications as indicated in the attachment to this license

-amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-7 is hereby amended to read as follows:

(2) -Technical Specifications The Technical Specifications contained in Appendices

~

A~ and B, as revised through Amendment No.11 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical

. Specifications.

3.

This license amendment is effective May 29, 1981.

FOR THE NUCLEAR REGULATORY COMMISSION b

a Robert A. Clark, Chief-Operating Reactors Branch #3 Division of Licensing

Attachment:

Changes to the Technical

. Specifications P

Date of Issuance: May 22, 1981 1

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f, ATTACHMENT TO LICENSE AMENDMENT AMEN 0 MENT NO.11 TO FACILITY OPERATING LICENSE NO. NPF-7 DOCKET NO. 50-339 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated. The revised pages are identified by Amendment. number and contain vertical if nes indicating the area of.

change. The corresponding overleaf pages are also provided to maintain document completeness.

Pages XVI XVII-6-1 6-la 6-2 6-3 6-6 6-7 6-8 6-9 6-10 6-11 6-12 6-13 6-20 l

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INDEX-DESIGN FEATURES SECTION PAGE 5.1'~ SITE Ex c 1 u s i o n ' A re a '................................................

5-1 Low Population Zone...........................................

5-1 5.2 CONTAINMENT Configuration...................;.............................

5-1 Design Pressure and Temperature...............................

5-1 5.3 REACTOR CORE Fuel Assemblies...............................................

5-4 Control Rod Assemblies........................................

5-4 1

5.4 REACTOR COOLANT SYSTEM Design Pressure and Temperature...............................

5 l I

Vo1ume........................................................

5-4 t

5.5 METEOROLOGICAL TOWER LOCATION.................................

5-5 l

5.6 FUEL STORAGE C r i t i ca 1 1 ty..................................................

5-5 l

0rainage.....................................................

5-5 l

Capacity.....................................................

5-5 t

5.7 COMPONENT CYCLE OR TRANSIENT LIMIT..'.........................

5-6

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f NORTH ANNA - UNIT 2 XV l

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l INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 RESPONSIBILITY................................................

6-1 6.2-ORGANIZATION 0ffsite.........................................................

6-l'

' Facility Staff.................................................

6-1 Safety Engineering Staff........................................

6-la-Shift Technical Advisor.........................................

6-la 6.3 FACILITY STAFF 00ALIFICATIONS................................

6-6 6.4 TRAINING.....................................................

6-6 6.5 REVIEW AND AUDIT' 6.5.1 STATION NUCLEAR SAFETY AND OPERATING COMMITTEE (SNSOC)

Function........................................................

6-6 Composition.....................................................

6-6 Alternates......................................................

6-6 Meeting Frequency...............................................

6-7 Quorum..........................................................

6-7 Responsibilities................................................

6-7 Authority.......................................................

6-8 Records.........................................................

6 6.5.2 SAFETY EVALUATION AND CONTROL ~(SEC) l Function........................................................

6-8 l

Composition.....................................................

6-9 r

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NORTH ANNA-UNIT 2' XVI Amendment No.11 i

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- INDEX~

ADMINISTRI.TIVE CONTROLS SECTION' PAGE-Consultants.....................................................

6-9 Meeting Freauency...............................................

6-9 Review.................................................

........ 9 I

l

. Authority.......................................................

6-10

. Records.........................................................

6-10 6.5.3 QUALITY ASSURANCE DEPARTMENT Function........................................................

6-11 Authority.......................................................

6-12 Records.........................................................

6-12 6.6 REPORTABLE OCCURRENCE ACTI0N................................

6-13 6.7 SAFETY LIMIT VIOLATION.......................................

6-13 6.8 PR0CEDyRES...........................................

6-13 6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REPORTS AND REPORTABLE OCCURRENCES.................

6-14 6.9.2 SPECIAL REP 0RTS............................................

6-18 6.10 RECORD RETENTION............................................

6-18 6.11 RADIATION PROTECTION PR0 GRAM................................

6-20 6.12 HIGH RADIATION AR A.........................................

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6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1.- The Station-Manager. shall be responsible for overall facility'. operation.

In hisl absence, the Assistant Station Manager shall be responsible for ove'.all facility operation.

During the absence of both, the Station Manager shall delegate in writing the succession to this responsibility.

6.1. 2 The Shift Supervisor (or during his absence from the Control Room, a designated individual) shall be responsible for the Control Room command function and shall be the only individual that may direct the. licensed activ-ites of licensed operators. ' A management direct've to this effect, signed by the Executive Vice President-Power, shall be reissued to all station personnel on an annual basis.

6.2 ORGANIZATION OFFSITE 6.2.1-The offsite organization for facility management and technical support shall be as shown on Figure 6.2-1.

FACILITY STAFF 6.2.2 The Facility organization shall be as snown on Figure 6.2-2 and:

a.

Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.

b.

Ac least one licensed Reactor Operator shall be in the control room when fuel is in the reactor.

In addition, while the unit is in MODES 1, 2, 3 or 4, at least one licensed Senior Reactor Operator shall be in the Control Room.

c.

A health physics technician 1 shall be On site when fuel is in the reactor.

,ALL CORE ALTERATIONS shall be observed and directly supervised by r

either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has ne other concurrent responsibilities curing this operfcion.

e.

A site Fire Brigade of at least 5 members shall be maintained onsite at all times #.

The Fire Brigade shall not include the minimum shift

'er.w shawa in Table 6.2-1 or any personrel required for other essential fer,ctions during a fire emergency.

The nealth physics technician and Fire Bricade comoosition may be less than the minimum requirement for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order l

to accommodate unexpected absence provided immediate action is taken to fill

.the required positions.

NORTH ANNA-UNIT 2 6-1 Amendment No. 11

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4 ADMINISTRATIVE CONTROLS

6.2.3: SAFETY ENGINEERING STAFF -(SES)-

FUNCTION 6.2.3.1 The SES'sha'll function: to examine ' plant.opefating characte: :, tics, NRC; issuances, industry advisories, Licensee Event Reports, and other sources

~

which may indicate areas.for improving plant safety.

COMPOSTTION ma.

6.-2.3.2 ;The SES.shall~be composed of at least-five dedicated,' full-time

.' engineers located onsite,

,.y RESPONSIBILITIES

A 6:2.3.3 The SES shall be responsible for maintaiai.:g surveillance of plant idtivities to provide independent verification

that these activities are performed correctly.and that. human errors are reduced as much as practical.

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,6;2.3.4 The SES shall map. detailed recommendations for revised procedures, equipment modificaticns,- or'other means of improving plant safety to.the Station Manager and the. Director-Safety Evaluation and Control.

l6.2.4 SHIFT TECHNICAL ADVISOR 6.2.4.1 The Shift Technical Advisor shall serve in an advisory capacity to

, Shift Supervisor on matters pertaining to the engineering aspects of assuring-safe operation of the unit.

6.2.4.2 The Shift Technical Advisor shall disseminate relevant operational l-experience identified by the SES.

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"Not responsible for sign off function.

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6-la Amendment No.11

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NORTH ANNA - UNIT '.

6-2 Amendmer t No.11 9

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I!ii NORTH ANNA - UNIT 2 6-3 Amendment No. 11 I

l PDDR DRIGINAL

~

di TABLE 6.'2-1 MINIMUM SHIFT CREW COMPOSITION

-WITH UNIT 1 IN MODE 5-OR 6 OR DE-FUELED POSITION

~ NUMBER OF INDIVIOUALS REQUIRED TO FILL POSITION MODES 1, 2, 3, & 4 MODES 5 & 6 a

a SS

.l 1

SRO 1-none.

R0 22 1

~

-A0 2

29

-STA 1.

none

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WITF UNIT'1 IN MODES 1, 2, 3, 0R 4 4

POSITION

-Nt;MBER OF INDIV10UALS REQUIRED TO FILL POSITION MODES 1, 2. 3, & 4 MODES 5 & b a

a SS l

y a

SRO.

l none b

R0 2

y b

A0

?

y a

STA-l none 1

a/ Individual may fill the same pt,sition of Unit 1.

b/ One.of'the two required individuals ~may fill the same position on Unit 1.

l l

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NORTH ~ ANNA-UNIT,2:;.;: ';'

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TABLE 6.2-1 (Continued)

SS - Shift Supervisor with a Senior Reactor Operators License on Unit 2.

-SR0 -' Individual with a Senior' Reactor Operators License on Unit 2.

RO - I dividual-with-a Reactor Operators License on Unit 2.

o A0 - Auxiliary Operator.

47A - Shift-Technical Aceisor Except for the Shift Supervisor, the' Shift Crew Composition may be one less than the minimum requirements of Table 6.2-1 fce a period of time not to exceed.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the Shift Crew Composition to within the minimum requirements of Table 6.2-1.

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 !! ODE 1, 2, 3 or 4, an individual (other than the Shift Technical Advisor) with a valid SRO license shall be designated to assume the Control-Room command function.

Durin; any absence of the Shift Supervisor from the Control Room while the unit is in MODE 5 or 6, an' individual with.a valid R0 license (other than the-Shift Technical Advisor) shall be designated to assume the Control Room command function.

Licensed operators shill:*

1.

Not work more than 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months straight, 2.

Not work niore than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in any 48-hour period, 3.

Not. work more than 7E hours in any 7-day ?criod,-

4.

Not work more than 14 consecutive days witnout having 2 consecutive days off.

Deviation frem these requirements may be authorized by tne Station Manager in accordance with established procedures and with documentation of the cause.

Overtime limits do not include t'.e shift turnover time.

l NORTH ANNA-UNIT 2 6-5

~.

. =, -,,,. - - -

,,. = -..,.

.nc

m 4

t ADMINISTRATIVE'CONTRLS Gj3~

' FACILITY STAFF QUALIFICATIONS 1 6.3.1' Each' member of the unit staff shall-~ meet or exceed the' minimum qualifications of ANSI N18.1_- 1971 for comparable ' positions and the supplemental requirements specified in the March 28, 1980 NRC letter.

to all1 licensees,-except for (1) the Supervisor - Health Physics who-shall. meet or exceed the qualifications of Regulatory Guide 1.8, September 1975 and (2) the Shift Technical Advisor who.shall.have a bachelor's degree or eonivalent'in a scientific or engineering discip-line with: specific-training in plant design, and response'and analysis of:the plant foritransients and accidents.

6.4 : TRAINING 6.4.1.The Station Manager is. responsible 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 identified.by-the SES.

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.

COMPOSITION

6. 5.1. 2 The SNSOC shall be composed of the :

Chairman:

Station' Manager.

Vice Chairman:

Assistant _ Station Manager l

. Member:

S perintendent-Operations 4

-Member:

Superintendent-Maintenance L

Member:

Superintendent-Technical Services Member:

Supervisor-Health Physics l

l ALTERNATE 5 i_

! 6. 5.1. 3 All alternate members shall be appointed in writing by the SNSOC Chairman to serve on a temporary basis; howe.or, no more than one alternate shall' participate as a voting member in SNSN activities at say one time.

(

NORTH ANNA-UNIT 2 6-6 Amendment No.ll y

l

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@MINISTRATIVECONTROLS MEETING FREQUENCY 6.5.1.4'-The'SNSOC shall meet at least once per calendar monta and as convened-by.the SNSOC Chairman or h's' designated alternate;

,i QUORUM 6.5.1;51 A ' quorum of. the SNSOC shall_ consist.of the Chairman or Vice-Chairman -

and~two members including alternates.

RESPONSIBILITIES 15.5.1.6 The. SNSOC shall be responsible: for:

a.

Review of 1) all procedures required by Specification 6.8.1 and

-changes-thereto, 2) all programs required'by Specification 6.8.'4-and changes thereto, 3) any other proposed procedures or changes thereto as determined by the Station Manager to affect nuclear safety.

b.

Review of all proposed. tests and experiments that affect nuclear-safety.

c.

Review of all proposed changes to' Appendix "A" Technical Specifications.

d.

Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.

e.

Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evaluation-and-recommendations'to prevent recurrence to the Manager-Nuclear Operations' and Maintenance and the Director-Safety Evaluation 'and Control.

f.

Review of events requiring 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months written notification to the Commission.

g.

Review of facility operations to detect pc.tential nuclear safety hazards.

i h.

Performance of special reviews, investigations or analyses and reports thereon as requested by the Chairman of the Station Nuclear Safety and Operating Committee.

i.

Review of the Piant Security Plan and implementing procedures and shall submit recommended changes to the Chairman of the Station Nuclear Safety and Operating Committee.

I j.

Review of the Emergency Plan and implementing procedures and shall j

submit recommended changes to the Chairman of the Station Nuclear i

Safety.and Operating Committee.

. NORTH ANNA-UNIT 2 6-7 Amendment No. 11

A ADMINISTRATIVE CONTROLS A'JTHORITY.

6.5.1.7 The SNSOC shall:

a.

Recommend to the-Station Manager written approval or ' disapproval of items' considered.under 6.5.1.6(a) through (d) above.

b.

-Render determinations in writing'with regard to whether or not each item considered under 6.5.1.6(a) through (e) above constitutes an unreviewed safety question.

c.

Provide written notification within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to Manager-Nuclear Operations and Maintenance and the Director-Safety Evaluation and Control.of disagreement between_the SNSOC and the Station Manager; however, the Station Manager shall have responsibility for.resolu-tion of such disagreements pursuant to 6.1.'1 above.

RECORDS

6. 5.1. 8 The SNSOC shall maintain written minutes of each meeting and copies-shall be provided to the Manager-Nuclear Operations and Maintenance and the Director-Safety Evaluation and Control.

6.5.2 3AFETY EVALUATION AND CONTROL (SEC)

' FUNCTION 6.5.2.1 SEC shall function to provide independent review of designated activities in the areas of:

a.

Nuclear power plant operations b.

Nuclear engineering c.

Chemistry and radiochemistry d.

Metallurgy.

e.

Instrumentation and control f.

Radiological safety f

g.

Mechanical and electrical engineering h.

Administrative controls and quality assurance practices i.

Other appropriate fields associated with the unique characteristics of the nuclear power plant NORTH ANNA-UNIT 2 6-8 Amendment No.11

g, v

a

-i ADMINISTRATIVE CONTROLS COMPOSITION.

l 6.5.2.2.TheLSECl staff shall be cemposed of the Director-SafetyzEvaluation and Control'and a. minimum of three individuals who are qualified c; staff specialists.~ Each SEC staff' specialist shall'have.an.' academic degree in an engineering or physical science field bd; in addition, shall.have a minimum of five_ years technical experience in one or more areas given'in Specification 6.5.~2.1.

These staff-specialists shall not be~ directly. involved in the.

licensing function.

I-CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the Director-Safety Evaluation -and Control to provide ' expert advice to the SEC.

MEETING FREQUENCY.

. t 6.5.2.5.-The-SEC staff shall meet at least once per calendar month for the purpose of fostering interaction of reviews regarding safety-related opera--

tional. activities.

' REVIEW 5.5.2.7 The following subjects shall be reviewed by SEC:

a.

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 3afety Analysis Report which are completed without prior NRC approval under the provisions of 10 CFR 50.59(a)(1).

This review is to verify that such changes, tests or experiments oid not involve a-change in the technical specifications or an unreviewed safety question as defined in 10 CFR 50.59(a)(2) and is accomplished by review of' minutes of the Station Nuclear Safety and Operating Committee and the design change program.

b.

Propcsed changes in procedures, proposed changes in the station, or proposed tests or experiments, any of which may involve a change in-

~

I the technical specifications or an unreviewed safety question as defined in 10 CFP 50.59(a)(2).

Matters of this kind shall be referred to the Oir ector-Safety Evaluation and Control by the Station Nuclear Safety'and Operating Committee following its review prior to implementa-tion.

c. - Changes in the technical specifications or license amendments relating to nuclear safety prior to imp % mentation excer; in those cases where the change is. identical to a previously reviewed proposed change.

NORTH ANNA-UNIT 2 6-9 Amendment No.ll

~

ADMINISTRATIVE CONTROLS REVIEW:(Cont'd) d.

. Violations an'd reportable ~occurre'nces such as:

1.

Violations of applicable codes : regulations, orders, Technical-

' Specifications, license requirements or internal procedures or-

-instructions having safety significance;

2.

Significant operating abnormalities or deviations from normal or-expected performance of station safety-related-structures', _

c systems, or components; and 3.

Reportable occurrences as defined.in the station Technical l.

Specification'6.9.1.8.

.I.

Review of events covered under this paragraph shall' include the results of-any investigations made'and recommendations resulting

' from such investigations to prevent or reduce the probability of recurrence of the event.

e.

The Quality' Assurance Department audit program at least'once per 12 months and audit reports.

f.

Any other matter-involving safe operation of the nuclear power l

. stations which a duly appointed subcommittee or committee member deems appropriate. for consideration, or~ which is referred to the Director-Safety. Evaluation and Control by the station Nuclear Safety and Operating Committee, g.

Reports and meeting minutes af the Station Nuclear Safety and Operating I Committee.

AUTHORITY 6.5.2.9 The Director-Safety Evaluation and Control shall repc.t to and advise the Manager-Nuclear Technical. Services, who shall advise the Vice President-Nuclear Op'erations on those areas of responsibility specified in Section 6.5.2.7.

,0.ECORDS

'6.5.2.10 Records of SEC activities required by Section 6.5.2.7 sh4ll 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 l

2.

Nuclear P:wer Station Managers 1.

Manager-Nuclear Operations and Maintenance l

I

[

NORTH ANNA-UNIT 2 6-10 Amendmeat No. 11

=

2).-

e r

~

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' ADMINISTRATIVE CONTROLS RECORDS (Cont'd) 4.

Manager-Nuclear Technical Services 5.

IManager-QualityfAssurance, Operations 6.

Others-that the Direct'or-Safety Evaluation and' Control: may designate.

~

6.5.3: QUALITY ASSURANCE DEPARTMENT' FUNCTION 6.5.? ~ : The Quality Assurance Department-shall: function to audit station activisies. -These audits shall encompass:

a.

The conformance of' facility operation to provisions contairied_within-the Technical Specifications and applicable' license conditions at

'least once per 12 months.

. b.

The performance, training and qualifications of the entire facility staff at>1eastionce per 12 months.

c.

The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months.

d.

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 months.

'The Station Emergency Plan and implementing procedures at least once e.

-per 24 months.

f.

The Station Security Plan and implementing procedures at least once per.24 months.

g.

Any other area of facility operation considered appropriate by the Executive Manager-Quality Assurance or the Senior Vice President-Power Operations.

h.

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

i.

An independent fire protection and loss prevention program inspection and audit'shall be performed at least cace per 12 months utilizing either qualified offsitt licensee personnel er an outside fire pro-tection firm.

j An inspection and audit of the fire protection and loss prevention program shall be performed by a qualified outside fire consultant at least o.nce per 36 months.

t 1

L NORTH ANNA-UNIT 2 6-11 Amendment No. li

_._.,_.__.._.__.,._...____._.a.__.

cc

,~

s k

ADMINISTRATIVE CONTROLS AUTHORITY 6.5.83.2: The Quality Assurance Department shall report to and advise the-Executive Manager-Quality Assurance,-wholshall advise the Senior Vice -

President-Power _ Operations on those areas of._ responsibility specified in Section 6.5.3.1.

RECORDS 6.5.3.3 Records of the Qualit'y Assurance Department audits shall be prepared

~

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 31 Manager-Nuclear Technica1' Services 4.

. Manager-Quality Assurance, Operations

~

5.

Director-Quality Assurance,. Nuclear Operations 6.

Director-Safety EvaluationLand Control ~

7.

. Supers; or of area audited 8.

Nuclear Power Station Resident Quality Control Engineer z

i l

[--

i-NORTH ANNA-UNIT 2-6-12 Amendment No. 11

s ADMINISTRATIVE CONTROLS 6.6 REPOR~ABLE' OCCURRENCE ACTICN 6.6.1' The followingiactions shall be'taken for REPORTABLE OCCURRENCES:

. 'a.

The Commission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.9.

. b.'

~Each REPORTABLE OCCURRENCE' requiring 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . notification to.the Commission shall be reviewed by the SNSOC and submitte5 to the Director-Safety Evsluation 'and Control and the Manager-Nuclear -

-Operations and Maintenanc;

6. 7 -SAFETY LIMIT VIOLATION 6.7.1 -The'following actions:shall be taken in the event-a Safety Limit'is violated:

Ta.

lThe facility shall be placed in at least HOT STANDBY within one

-hour.

b.

The NRC Operations Center shall be notified.by telephone as soon as possible and in all cases'within one hour.

The Manager-Nuclear Operations and Maintenan

. and the Director-Safety Evaluation and Control shall be notifieo within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

c.

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, d.

The Safety Limit Violation Report shall be submitted to the Commission, the Director-Safety Evalastion and Control and the Manager-Nuclear Operations and Maintenance within 14 days of-the violation.

6.8 PROCEDURES AND PROGRA"S

~

6.8.1 ' Written procedures shall be established, implemented and maintained covering the activities referenced below:

a.

The applicable procedures recommended in Appenc;x "A" of Regulatory Guide 1.33, Reiision 2, February 1978.

b.

Refueling operatiait.

, NORTH ANNA-UNIT 2 6-13 Amendment No. 11 1.

w-r.

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+

y-., -.,<-w

h

-l

-AMINISTRATIVE CONTROLS l

c.

Surveillance and test activities'of safety related equipment.

= d.

Security Plan implementation.

e.

Emergency Plan implementation.

' f.

Fire-Protection Program Implementation.

-6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall be reviewed by the.SNSOC and approved by'the LStation Manager prior to implementation and raviewed periodically.as yet forth in administrative procedures.

- 6.8.3 Temporary _ chang [s to procedures of E.8.1.above may be made provided:

a.

The. intent of the original procedure is not altered.

b.

The change'is. approved by two members of the plant supervisory staff, at least one. of whom holds a Senior Reactor Operator's License on the unit ~affected.

c.

'The change is documented, reviewea by the SNSOC and approved by the

, Station Manager within 14 days of implementation.

6.8.4 Tho following_ programs shall be established, implemented, and maintained:

a.

Primary Coolant Sources Outside Containment 14 program to reduce' leakage from those portions of systems outside contain-ment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. The systems include the recirculation spray,~ safety injection, chemical and volume control, gas 4

stripper,.and hydrogen recombiners.

The program shall include the following:

(i) Preventive maintenance and periodic visual inspection requirements and (ii)

Integrated leak test requirements for each system at refueling cycle intervals or less.

t

[

' NORTH-ANNA - UNIT 2 6-14

ADMINISTRATIVE CONTROLS Each REPORTABLE OCCURRENCE submitted to the Commission.

c.

d. -

Records of surveillance activities, inspections and calibrations required by these Technical Spe:ifications.

Records of changes nada to Operating Procedures.

a..

f.

Records of. radioactive shipments.

Recordt of sealed source leak tests and results.

g.

h.

Records of annual physical inventory of all sealed source material of record..

~

6.10.2 The fol".owing records shall be retained for the duration of the Facility Operating License:

Records and drawing changes reflecting facility design modifications a.

meds to systems and equipment described in the Final Safety Analysis Report.

b.

Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.

c.

Records of facility radiation and contamination surveys.

d.

Records of radiation exposure for all individuals entering radiation contro1 areas.

Records of gaseous and liquid radioactive material release to the e.

environs.

f.

Records of transient or operational cycles for those facility components identified in Table 5.7-1.

g.

Records of reactor tests and experiments h.

Records of training and qualification for current memoers of the plant staff.

1.

Records of in-service inspections performed pursuant to these Technical Specifications.

j.

Records of Qua'ity Assurance activities required by the QA Manual.

k.

Records of the service lives of all hydraulic snubbers listed on Table 3.7-4a including the date at which the service life commences.

(This requirement commences with the Full Power License.)

NORTH ANNA - UNIT 2 6-19

,,.-,,.,.~.---.-

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+

~

4

~

4 L

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i

~

ADMINISTRATIVE CONTROLS'

. Recordsy ofL reviews? performe' iforcchanges.made -tof procedures f or 1.

d p,

equipment;or reviews of; tests and Wxperiments pursuant = ton 10-CFR 50.~59.

' m.

/ Records'of meetings of the;SNSOC.

t

<n.

Records'of meetings!of-the' System Nuclear Safety;and Operating

Committee-to issuance ofcAmendment;No. _

o.

.' Records of' secondary water?samplingfand water-quality.

h

^

?

p.

RecordsJ for Environme'ntal Qualification which are: covered under; the :

.l-provisions of; Paragraph:2.C(4)(e);of License No.n.NPF-7.

6.11 RADIATION PROTECTION' PROGRAM Procedures -for personnel radiation protection shall be prepared ' consistent..

with the~ requirements _of 10 CFR Part 20s and shall be' approved, maintained and-adhered to for all; operations involving personnel radiation exposure.

6.12 HIGH' RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal". required by paragraph.20.203(c)(2) of 10.CFR 20, each high. radiation area in which the' intensity of radiation is greater.than 100 mrem /hr but less than 1000 mrem /br

~

shal.1-be barricaded and conspicuously-posted as a high radiation area and entrance thereto shall beicontrolled by requiring issuance of a Raciation' Work

~Any individual or group.of individuals permitted to' enter such areas-

' Permit.*

~

j-shall be prov_ided-with or. accompanied by one'or more of-the following:

'a.

A radiation monitoring devi_ce which continuously indicates the.

L radiation dose rate in the area.

b.

-A radiation monitoring device which continuously integrates the_

i radiation dose rate in the area and alarms when a preset integrated dose is received.. Entry _into such areas wilia this monitoring device may be made after the dose rate level in the area has been f

istablished and personnel have been made knowledgeable of them.

{

l' c.

An individual qualified in the protection procedures who is ecu'pped with a radiation dose rate monitoring device.

This individual shall-jz be responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at

{

the frequency specified by the_ facility Health Physicist in the Radiation Work Permit.

I e

l i

L

^ Health Physics personnel or personnel escorted by Health Physics personnel l

p shall be_ exempt from the RWP issuance recuirement during the performance of their assigned radiation protection duties, provided they comply with approved j

radiation protection' procedures for entry in high radiation areas.

Ofdst d id Md m tidt 7, Jggg i

NORTH ANNA-UNIT 2 6-20 Arendment No li i

l; j

.e

~_ft, Q --.. "

'M ATTACHMENT'TO LICENSE AMr.NDMENT:

AMENDMENT ::0.11 TO FACILITY.0PERATING LICENSE NO. 'NPF-7 DOCKET NO. 50-339-

. Reolace the following pages-of 'the' Appen' dix "B" Technical Specifications with :the enclosed pages as indicated. : The' revised pages are identified by Amendment number ~and contain vertical. lines indicating the area of change.

~

P a ges '.

I-i

.I-ii I-5-1 1-5-2 I-5-3 LI-S I-5-5 i

1 I

f f

~..

- S, TABLE OF CONTENTS

. Pm 1-1 11.0) DEFINITIONS......................................................

L2.0 LIMITING CONDITIONS FOR'0PERATION................................

2-1 2.1

.Non-Radiological...............................'.............

2-1 2.2 Radioactive Effluents.......................................

2-1

-2i2.1 Specifications for Liquid Waste Effluents.........

'2-2 2.2.2-

~ Specifications forl Liquid.W.'ste Sampling and Monitoring..................................

2-3

2.2.3

_ Specifications for Gaseous. Waste Effluents........

2-7

)

2. 2. 4.-

~ Specifications for Gaseous Waste Sampling and Monitoring.................

2.2.2.5-Specifications. for Solid *'.:n.e Handling 4

and Disposal....................................

2-17 3.0 ENVIRONMENTAL SURVEILLANCE.......................................

3-1 3.1 Non-radiological Surveillance......................

3-l' 3.1.1 --

Abiotic - Aquatic........................

3.......

3.1.2-Biotic Aquatic..........................

3-1 3

3.1.3 Abiotic - Terrestrial....................

3-1 3.1. 4_ -

Onsite Meteorology Monitoring...........

3-1 3.2. Radiological Environmental Monitoring.......................

'3-2 4.0 SPECIAL SURVEILLANCE AND STUDY ACTIVITIES........................

4-1

-5.0 ADMINISTRATIVE CONTR0LS..........................................

5-1' 5

~5.1

' Responsibility..............................................

5-1 5.2 Organization................................................

5-1 5.3 Review'and Audit............................................

5-1 5.3.1 Station Nuclear Safety and Operating Committee (SNS0C).........................................

5-1 5.3.1.1 Function........................

5-1 5.3.1.2 Responsibility.........................

5*

5.3.1.3 Authority...............................

5a 5.3.1.4 Records.................................

5-3 i

f f

r i

I-i Amendment No. 11 i

I dg l

4 TABEE OF CONTENTS'(Cont'd);

~

Pase' 15.3.2 Quality Assurance Department......................

5-4 l

-5.3.2.'1 Function................................

5-4 5.3.2.2 Audits..................................

5-4 15.3.2.3 Records.................................

5-4' 5.3.3 Safety Evaluation and Control (SEC)...............

'5-4 l

5.3.3.1 Function................................

5-4 5.3.3.2 -

Keview..................................

5-4

-5.3.3.3

. Re s p on s ib ility..........................

5-5 5.3.3.4 Authority...............................

5-5 5.3.3.5 Records.................................

5-5 5.4 State and Federal Permits and Certificates..................

5-5

'5.5 Procedures..................................................

5-5 5.5.1 Written Procedures................................

5-5 5.5.2 Operating Procedures..............................

5-5 5.5.3 Procedures for Environmental Surveillance -

Radiological....................................

5 5.5.4

-Procedures for Environmental Surveillance -

Nonradfological.................................

5 5.5.5' Quality Assurance of Program Results..............

5-6 5.5.6 Changes in Procedures, Station Design or Operation.......................................

5-6 5.5.7 Consistency with Initially Approved Programs......

5-7 5.6. Station Reporting Requirements..............................

5-7 15.6.1 Routine Reports...................................

5-7 5.6.1.1 Annual Environmental Operating-Report...

5-7 5.6.1.2 Radioactive Effluent Release Report.....

5-8 5.6.2 Nonroutine Reports..........................

5-9 5.6.2.1

.Nonroutine Non-Radiological Environmental Operating Report......................

5-9 5.6.2.2 Nonroutine Radiological Environmental Ope ra ting Repo rts....................

5-10 5.6.3 Changes in Environmental Technical Specifications.

5-11

-5.6.4 Changes in Permits and Certifications.............

5-11 1

5.7 Records Retention...........................................

5-11 1

I-ii Amendment No. 11

8

-5.0 IADMINISTRATIVE CONTROLS

'i Administrative controls below' apply to Appendix B PartLI only.

I~5.11 Responsibility.

~The responsibility for implementing the Environmental Techneial Specifications!

-is' assigned to the Manager-Nuclear Operations and Maintenance at the corporate

~

. level and to the Station Manager at the station level. The Superintendent'--

Operations shall be. responsible-for ensuring that:the station is operated in accordance with the Limiting Conditions of Operation. The Station Supervisor -

Health Physics shall be responsible-for the radiological environmental.

surveillance requirements. The Executive Manager of. Environmental Services l

~

1shall be responsible for providing services which will fulfill the non-radiological' environmental surveillance requirements.

LS.2 Organization The relationship between the Nuclear Operations Department and the-Environmental Services Department is shown in Figure 5.2-1.

5.3 Review and Audit 5.3.1 Station Nuclear Safety-and Operating Committee (SNSOC)

'5.3.1.1 Function The ai3)C, as described in Section 6.5.1 of Appendix A of this license, shall function to advise the Static-Manager on matters related to the environmental-impact of the station.

With the SNSOC is exercising its responsibility for non-radiological aspects of the ETS, the Station Biologist or his alternate shall 'oe consulted.

I 5.3.1.2 Responsibi:ity The SNSOC shall be responsible for:

-a.

Coordination of the Environmental Technical Specifications with the Safety Technical Specifications (Appendix A) to avoid con-flicts and maintain consistency.

b.

-Review of changes to the Environmental Technical Specifications and the evcluation of the environmental impact of the change.

1 I-5-1 Amendment No. Il i

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3-g aan al P00R ORIGINAL I-5-2 Amendment No. Il

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-1 c.

Review of proposed written procedures ~ required by Section 5.5.2 L

sad 5.5.3'below and changes thereto,Lwhich affect the. environmental.

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' timpactiof the; station.

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(['_ -

' d.' L Review of proposed changes to -station' systems to determine ~ the environmental impact of:the' changes.

te.

? Investigation of all reported instances of violation of the Environmental Technical Specifications; and where the investiga-1

. tion indicates, evaluation and formulation of recommendations;to; prevent recurrence.

f.

' Review. of environmental monitoring programs to detect potential or. existing significant adverse environmental impacts-that have not.been evaluated, or that are significantly greater.than that D

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evaluated b ;the Commission.

i 15.3.1.3' Authority

.The'SNSOC-shtll:

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'a.

Review the environmental evaluation of all changes described in Section 5.3.1.2 a, b and e, above. When.the evaluation indicates that such activitiy may. result in a significant adverse environ-mental impact:that was not e aluated, or that is significantly greater; than;that evaluated by the Commission, the SNSOC shall ensure that a written evaluation of such activities is' provided -

to and prior. approval is obtained from the Director of Nuclear

' Reactor Regulation for the activities.

b.

If the SNSOC determines that, unexpected harmful effects or evidence of irreversible. damage are occurring as a result of operation of the station, the SNSOC shall ensure that an acceptable analysis of the ' problem and a ' plan of action to eliminate or significantly r

reduce the harmful effects or damage is submitted to the Commission

'for review and approval.

-c.

Review written reports prepared as a result of investigations and reviews conducted under 5.3.1.2 a, e and f.

.-5.3.'I.4

' Records The SNSOC shall maintain written minutes of each meeting and copies shall'be'provided to the Director-Safety Evaluation and Control.

1' l

l

~

I-5-3 Amendment No. 11 i

.y a.

15.3.2-Quality Assurance Department 5.3.2.1

' Function The Quality Assurance Department'sh'all perform independent' audits of' the' implementation of the Environmental Technical ~ Specifications.

+

523.2.2' Audits

Thelfollowing audits shall be completed:

a.

The conformance of facility operation to provisions contained within these Environmental Technical Specifications and applica--

'ble; license conditions at least once per 12 months.

b.

The performance, training and qualifications of the facility staff involved in ensuring and monitoring compliance with these Environmental Technical Specifications at least once per 12 months.

c.

The results of action'taken to correct deficiencies occurring in facility equipment, structures, systems'or method of operation that affect the environmental' impact of the station at least once.

per.12' months.

5.3.2.3 Records Provide a written report of the results of the audits required by 5.3.2.2 above to'the SNSOC, the Director-Safety Evaluation and Control.

and the Station Manager.

5.3.3 S fety Evaluation and Control (SEC) 5.3.3.1

-Function SEC, as described in Section 6.5.2 of Appendix A of this license, l

shall function to provide independent review of designated activities related to the environmental impact of the station.

5.3.3.2 Review l

SEC shall review and, where necessary, comment on the results of the reviews conducted by the SNSOC and the independent audits conducted by the Quality Assurance Department.

I 1

I-5-4 Amendment No. 11

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.5.3.3.3:. Responsibi7 g.

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SEC:has the responsibility for ensuring, through appropriate

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reviews, that.the cstation is operated' in accordance with~ the requirements :

tof.this licensenand. applicable NRCrregulations.-

5'.3.3'.41 7AutNority

^

The~ Director-Safety Evaluation and Control.shall' report to'and-advise the Manager-Nuclear Technical Services, who shall advise the Vice

'.: President-Nuclear Operations on those areas. relating"to the environmen-:

2

^tal impact of the station.

5.3.3.5 Records -

~

The records of-SEC'activitief relating to'the environmental' impact-of the station:shall be~ prep. ired and maintained in the SEC files cand. a summary shall be disseminated as indicated below each calendar month.

1.

!Vice President: Nuclear Operations 12.

Nuclear. Power Station Managers..

3.

1 Manager-Nuclear Operations and. Maintenance.

4.

. Manager-Nuclear Technical Services 5.

Manager-Quality Assurance, Operations 6.

.0thers that the Director-Safety Evaluation and Control may designate.

-5.4'

' State and Federal Permits and Certificates

~

None 5.5 Procedures l

5.5.1:

Written Procedures i

Detailed written procedures, including applicable checklists and instructions,- shall'be prepared and -followed for all activities involved in carrying out the Environmental Technical Specifications as defined i

in Sections 5.5.2, 5.5.3, and 5.5.4, below. Procedures shall incluse sampling, data recording and storage, instrument calibration, measure-ments and analysea, and actions to he taken when limits are. approached t

or exceeded.. Testing frequency of any alarm shall be included. These frequencies shall be determined from experience with similar instru-i ments in similar environments and from manufacturer's technical manuals.

I 5.5.2 Operating Procedures

. Plant standard operating procedures shall include provisions, in addition tai.the procedures specified in Section 5.5.1, to ensure that all plant systems and components are operated in compliance _with the

. Limiting Conditions of Operations established as part of the Environ-mental Technical Specifications.

I-5-5 Amendment No. 11

_. _.. _. _ _.. _ _. _ _ _ _ _.. _. _.. _, _ _ _,

ML20004C392

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