ML20065E421

Amends 140 & 123 to Licenses NPF-4 & NPF-7.respectively, Adding NRC Std Fire Protection License Condition to OLs & Relocating Fire Protection Requirements from Tech Specs to Updated FSAR

ML20065E421
Person / Time
Site:	North Anna   (NPF-04-A-140, NPF-07-A-123, NPF-4-A-140, NPF-7-A-123)
Issue date:	09/13/1990
From:	Berkow H Office of Nuclear Reactor Regulation
To:
Shared Package
ML20065E428	List: ML20065E421 ML20065E431
References
NUDOCS 9010020163
Download: ML20065E421 (36)

Text

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i VIRGINTA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE 1

DOCKET No. 50-338 NORTH ANNA POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.140 License No. NPF-4 1.

The huclear Regulatory Comission (the Comission) has found that:

i A.

The application for amendment by Virginia Electric and Power Company 1

et al., (the licensee) dated June 26, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; i

B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; 1

C.

Thereisreasonableassurance(i)thattheactivitiesauthorized 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 Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

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Accordingly, license condition 2.0.(3)t. is hereby added to Facility i

Operating License No. NPF-4 to read as follows:

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Fire Protection VEPC0 shall implement and maintain in effect ell provisions of the approved fire protection program as described in the Final Safety i

Analysis Report for the facility and as approved in the SER dated February 1979 subject to the following provisions The licensee may make changes to the approved fire protection i

i-program without prior approval of the Connission only if those changes would not adversely affect the ability to achieve and l

maintain safe shutdown in the event of a fire.

3.

In addition, the license is amended by changes to the Technical Speci-

)

fications as indicated in the attachment to this license amendment, i

and paragraph 2.0.(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.140, are hereby incorporated in the license. The licensee shall operate the facility in l

accordance with the Technical Specifications.

4 This license amendment is effective as of the date of issuance and shall be implemented within 30 days.

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

Attachment:

Changes to the Technical Specifications Date of Issuance: September 13, 1990

ATTACHMENT TO LICENSE AMENDMENT NO. 140_

TO FICILITY OPERATING LICENSE NO. NPF-4 DOCKET NO. 50-338 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 lines indicating the area of change.

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

Eagg IV Yllia XV 3/4 3 52 through 3/4 3-53a (deleted) 3/4 7-75 through 3/4 7-84 (deleted)

B 3/4 3-3 B 3/4 7-9 b 3/4 7-10 6-la 6-7 6-13 6-21 2

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INDEX LIMITING CONDITIONS TOR OPERATION AND SURVEILLANCE REQUIREKENTS t

SECTION Pact 3/4.2 P0k'IR DISTRIBUTION LIMITS 3 /4. 2.1 Axial Flux Difference.................................. 3/4 2-1 3/4.2.2 Heat Flux Mot Channel Tactor............................ 3/4 2-5 3/4.2.3 Nuclear Enthalpy Rot Channel Tactor..................... 3/4 2-9 3/4.2.4 Qua d ran t P owe r Tilt Ra t io............................... 3 /4 2-12

[

3/4.2.$ DNB Parameters.......................................... 3/4 2-14 f

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f 3 /4. 3 INSTRUMINTATION 5

3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION..................... 3/4 3-1 3/4.3.2 ENGINEERED SATETY TEATURE ACTUATION SYSTEM INSTRUMENTATION

.......................................... 3/4 3-15 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring.................................... 3/4 3-35 Novable Incore Detectors................................ 3/4 3-39 Seismic Instrumentation................................. 3/4 3-40 Me te orological Ins t rumenta t ion.......................... 3 /4 3-43 Auxiliary Shutdown Panel Monitoring Instrumentation..... 3/4 3-46 Ac cident Monit oring Ins t rumenta tion..................... 3 /4 3-49

.s Loos e Pa rts Moni tori ng Sys tem.......................... 3/4 3-56 Explosive Gas Monitoring Instrumentation...............

3/4 3 59 l

3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION Startup and Power Operation............................. 3/4 4-1 B o t S t a ndby............................................. 3 /4 4 -2 S hu t d own................................................ 3 / 4 4 -3 I s o l a t e d Lo o p........................................... 3 /4 4 -4 Isolated Loop Startup......................,............ 3/4 4-5

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NORTH ANNA - UNIT 1 IV Amendae t No. 3, Jg, JJ, 4 $, 195, VN, 0,

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NORTH ANNA UNIT 1 Villa AmendmentNo. 3,p1,140, i

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i INDEX BASES SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE.......................................

B 3/4 7-1 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION...,. B 3/4 7-4 3/4.7.3 COMPONENT COOLING WATER SUBSYSTEM...................

B 3/4 7-4 5

3/4.7.4 SERVICE WATER SYSTEM................................

B 3/4 7-4 3/4.7.5 ULTIMATE HEAT SINK..................................

B 3/4 7-5 3/4.7.6 FLOOD PROTECT 10N....................................

B 3/4 7-5 3/4.7.7 CONTROL ROOM EMERGENCY HABITABILITY.................

B 3/4 7-5 3/4.7.8 SAFEGUARDS AREA VENTILATION SYSTEM..................

B 3/4 7-5 3/4.7.9 RESIDUAL HEAT REMOVAL SYSTEMS.......................

B 3/4 7-6 3/4.7.10 HYD RAUL I C S NU B B E RS..................................

B 3/4 7-6 3/4.7.11 SEALED SOURCE CONTAMINATION.........................

B 3/4 7-7 3/4.7.12 SETTLEMENT OF CL ASS 1 STRUCTURES.................... B 3/4 7-7a 3

3/4.7.13 GROUNDWATER LEVEL - SERVICE WATER RESERVOIR.........

B 3/4 7-9 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES........................................

B 3/4 8-1 3/4.C.2 ONSITE POWER DISTRIBUTION SYSTEMS...................

B 3/4 8-1 i

3/4.9 REFUELING OPERATIONS L

3/4.9.1 BORON CONCENTRATION.................................

B 3/4 g-1 l

3/4.9.2 INSTRUMENTATION.....................................

B 3/4 9-1 NORTH ANNA - UNIT 1 XV AmendmentNo.3.5.?f.

140 lr l

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$ECTION PAGE 3/4.9.3 DECAY TIME..............................................

B 3/4 9-1 t

3/4.9.4 CONTA! MENT BUI LDING PENETRATIONS.......................8 3/4 9-1 3/4.9.5 ComuN I CAT ! 0NS..........................................

8 3/4 9-1 3/4.9.6 MANIPULATOR CRANE OPERABILITY...........................

B 3/4 9-2 3/4.9.7 CRANE TRAVE L - $ PENT FUE L P3 7...........................B 3/4 9-2 3/4.9.B RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION...........B 3/4 9-2 3/4.9.9 CONTAINMENT PURGE AND EXHAUST !$0LATION SYSTEM.......... B 3/4 9-2 3/4.9.10 and 3/4.9.11 WATER LEVEL REACTOR VESSEL AND $ PENT FUEL PIT..............................................

B 3/4 9-3 3/4.9.12 FUEL BUILDING VENTILATION SYSTEM........................

B 3/4 9-3 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 $HUTDOW MA RG 1 N.........................................

t 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS................................................

8 3/4 10-1 3/4.10.3 PHYSICS TESTS.....................................

S 3/4 10-1 3/4.10.4 REACTOR COOLANT L00PS...................................

B 3/4 10-1 NORTH ANNA - UNIT 1 XVI Amendment No. W. 138

' INSTRUMENTATION BASES 3/4.3.3.6 POST-ACCIDENT INSTRUMENTATION The OPERABILITY of the post-accident instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables following an accident.

3/4.3.3.9 LOOSE PARTS MONITORING SYSTEM OPERABILITY of the Loose Parts Monitoring System provides assurance that loose parts within the RCS will be detected. This capability is designed to ensure that loose parts will not collect and create undesirable flow blockages.

NORTH ANNA - UNIT 1 B 3/4 3-3 Amendment No. 3.)p; Jpp 140

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e NORTH ANNA UNIT 1 B 3/4 3 4 Amendment No. M.130, M

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PLANT SYSTEMS I

BASES l

3/4.7.13 GROUNDWATER LEVEL-SERVICE WATER RESERVOIR A program to monitor grounJwater levels in the area of the service water reservoir has been established to ensure that the integrity of the l

service water reservoir embankments and pumphouse is akintained.

i Groundwater threshold levels have been established based on historical groundwater data available in 1977. These levels are suf-i ficiently conservative to ensure that the service water reservoir and pumphouse will perform their intended function. An engineering evalua-tion will be performed if these threshold values are exceeded, to determine if there is any substantive cause to believe that any aspect of the service water reservoir, dike or pumphouse will not perform its intended function.

A conclusion to this effect, and the appropriate I

corrective actions to be perforwed, will be reported to the Commission.

The groundwater threshold levels are periodically reviewed to determine whether a changing groundwater environment warrants a change in threshold levels.

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NORTH ANNA - UNIT 1 B 3/4 7-9 AmendmentNo.A,140

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1 NORTH ANNA UNTT 1 33/4710 AmendmentNo. 31140, w

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6.0 AD3t!'llt9RATIVE CONTROLS 6.1 RESPON5!EILITY 6.1.1 The Station Manager shall be responsible for overall facility operation.

In his absence, the Assistant Station Manager (Operations and Maintenance) shall be responsible for overall facility operation. During the absence of i

both, the Station Manager shall delepote 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 comand function 1

and shall be the only individual that may direct the licensed activities of licensed operators. A management directive to this effect signed by the Senior Vice President -Nuclear, shall be reissued to all slation personnel on l

an annual basis.

6.2 ORGANIZATION i

4 ON51TE AND OFr$1TE ORMN12AT10N 0.2.1 Onsite and Offsite Organization An onsite and an offsite organization shall be established for facility operation and corporate management. The onsite and offsite organization shall include the positions for activities affecting the safety of the nuclear power plant.

a.

1.ines of authority, responsibility, and comunication shall be established and def'ned for the highest management levels through intermediate levels to and including all operating orga61 ration positions. These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the UFSAR.

b.

The Station Hanager shall be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant, The Vice President - Nuclear Operations shall have corporate l

c.

responsibility for overall plant nuclear safety end shall take any measures needed to ensure acceptable performance of tha l

staff in operating, maintaining, and providing technic 41 support to the plant to ensure nuclear safety.

d.

The management position responsible for training of the operating staff and the management position responsible for the quality j

assurance functions shall have sufficient organizational freedom including sufficient ~ independence fromeost and schedule when opposed to safety considerations.

i MORTH ANNA - UNIT 1 6-1 gdment loos. 3,78,7),pp.75,pf 4

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ADMINISTRATTVE CCNm0LS i

a. The management position responsbie for health physios 6 hall have droct moness to met onsite individual having responsibility for overall facility management. Health physics i

rsonnel shall have the authority to cease any work activity when worker safety is ardized or in the F ent of unnecessary personnel etion exposures.

FACILITY STAFF 4.2.2 The Faculty orgenlaation shall be as shown in me UFSAR.

s. Each on duty shift shall be composed of at least the minimum enitt crew composition shown in Table 4.21.

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 1,2,3 or 4, at least one lleensed Senior Reactor Operator shall be in the Control Room.

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c. A health physics techniciano shall be onsite when fuel is in me reactor.

d. ALL CORE ALTERATIONS shall be observed and drectly supervised by edher a lleensed l

Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.

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The health physics technician composition may be less than me minimum requirements for a l

period of time not to escoed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence provided immediate action is taken to fill the required positions.

NORTH ANNA. UNIT 1 61a Amendment No. 33,73,87,99, 140

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'ADMINISTMTIVE' CONTROLS k.

Review of every unplanned onsite release of radioactive material to the environs including the preparation of' reports covering evaluation, reconnendations and disposition of the corrective i

action to prevent recurrence and the forwarding of these reports to the Vice President-Nuclear Operations and the Management d

Safety Review Committee.

1.

Review changes to the PROCESS CONTROL PROGRAM and the 0FFSITE DOSE CALCULATION MANUAL.

m.

Revie w of the Fire Protection Program and implementing procedures and shall submit ~reconnended changes to the Station Manager.

AUTHORITY 6.5.1.7 The SNSOC shall:

a.

Provide written approval or disapproval of items considered under 6.5.1.6(a) through (c) above.

SNSOC approval shall be certified in writing by an Assistant Station Manager, 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vice President-l Nuclear Operations and the Management Safety Review Comittee (MSRC) y of disagreetnt between the SHSOC and the' Station Ranager; however, the Station Manager shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.

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RECORDS l

l-6.5.1.8 The $NSOC shall inaintain written minutes of ' ach meeting and copies shall be provided to the Station Manager, Vice Pr6 $1/ent-Nuclear Operations and the MSRC.

6.5.2 MANAGEMENT SAFETY REVIIW COMMITTEE (MSRC)

FUNCTION 6.5.2.1. The MSRC shall function to provide' independent review.of designated activities in the areas of:-

a.

Station Operations b.

Maintenance' c.

Reactivity Management d.

Engineering e.

Chemistry and Radiochemistry l

f.

Radiological Safety g.

Quality Assurante Practices -

h.

Emergency Preparedness NORTH' ANNA - UNIT 1 6-7 Amendment No. 77.39,#888, 7).1 8,

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140

ADMINISTRATIVE CONTROLS COMPOSITION 6.6.2.2 The MSRC shall be composed of the MSRC Chairman and'a minimum of four MSRC members.

The Chairman and all members of the MSRC shall have that meet the requirements of Section 4.7 of ANSI /ANS 3.1 1979 Rev. qualifications 1 (Draft).

-ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the MSRC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in MSRC activities at any one time.

CONSULTANTS 6.5.2.4 Consultants should be utilized as deterr.ined by the MSRC Chairman to provide expert advice to the l'SRC.

MEETING FREQUENCY 6.5.2.5 The MSRC shall meet at least once per calendar quarter.

QUORUM.

6.5.2.6 The minimum quorum of the MSRC necessary for the performance of the MSRC review and audit functions of these Technical Specifications shall consist of the Chairman or his designated alternate and at least 50% of the MSRC members including alternates. No more than a minority of the quorum shall have line responsibility for operation of the unit.

_ REVIEW-6.5.2.7 The MSRC shall be responsible for the review of:

The safety evaluations for 1) changes to procedures, equipment a.-

or systems and 2) tests or experiments completed under the provision of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question,

b..

Proposed changes to procedures, equipment or systems which involve an unreviewed safety question'as defined in Section 50.59, 10 CFR, L

proposed tests or experiments which involve an unreviewed c.

safety question as defined in Section 50.59, 10 CFR.

d.

Proposed changes to Technical Specifications or this Operating License.

NORTH ANNA - UH11 1 6-8 Amendment No. !!,17,H,97,135, 1

ADMINISTRATIVE CONTROLS c.

Surveillance and test activities of safety related equipment.

d.

Security Pin implementation.

e.

Emergency Plan implementation.

f.

Fire Protection Program implementation.

9 PROCESS CONTROL PROGRAM implementation.

h...

OFFSITE DOSE CALCULATION MANUAL implementation.

1. - Quality Assurance Program for effluent and environmental monitoring, using.the guidance in Regulatory Guide 1.21, Revision'1. June 1974 and Regulatory Guide 4.1, Revision 1 April 1975.

6.8.2 Each procedure of 6.8.1 above, except 6.8.1.d. 6.8.1.e; and 6.8.1.f and l-i changes thereto, shall be reviewed.and ' approved by the $NS00 prior to implemen-tation and reviewed periodically as satt forth in administrative procedures..

Procedure of 6.8.1.d. 6.8.1.e. and 6.8.1.f shall be reviewed a'nd approved as l

per 6.5.1.6.1, 6.5.1.6.j, and 615.1.6.m.

SNSOC approval ~shall be certified in writing by an Assistant Station Manager.

6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:

a.

The intent of the or%inal 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 Operater's License on the unit affected.

c.

The change is documented, reviewed, and approved by the SNSOC a

within 14 days of implementation. SNSOC approval shall be certified in writing by an Assistant Station Manager.

6.8.4 The following programs shall be established, implemented, and maintained:

a.

Primary Coolant Sources Outside Containment.

A program to reduce leakage from those portions of-systems outside containment 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 stripper.

and hydrogen recombiners. The program shall include the following:

(1) Preventive maintenance and periodic visual inspection requirements, and L

(ii) Integrated leak test requirements-for each system at refueling cycle intervals or less.

I NORTH ANNA - UNIT 1 6-13 Amendment No. 5,78,32,($1A,140, 1

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ADMINISTRATIVE CONTROLS b.

In-Plant Radiation Monitoring A program which will ensure the capability to accurately detemine the airborne iodine concentration in vital areas under accident i

conditions. This program shall include the following:

i

'(1) Training of personnel, (ii) Procedures for monitoring, and (iii) Provisions for maintenance of sampling and analysis equipment.

c.

Secondary Water Chemistry A program for monitoring of secondary water chemistry to inhibit steam generator tube degradation. This program shall include:

(i)

Identification of a sampling schedule for the critical-variables i

and control points for these variables, (ii)

Identification of the procedures used to measure the values of the critical variables, (fii)

Identification of process sampling points, (iv) Procedures for the recording and management of data.

(v) Procedures defining corrective actions for all control point chemistry. conditions, (vi) A procedure identifying (a) the authority responsible for. the interpretationofthedata,and(b)thesequenceandtiming i

of administrative events required to initiate corrective action, and (vii) Monitoring of the,tondensate at thidischarge of the conden-sate pumps for evidence of condenser inleakage. When condenser inleakage is confimed, the leak shall be repaired, plugged,,or isolated within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />, d.

Post-Accident Sampling

'A program which will ensure the capability.to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples under

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accident. conditions. The program shall include tne following:

(i) Training of personnel.

r (ii) Procedures for sampling and analysis.

(iii) Provisions for maintenance of sampling and analysis equip-ment.

NORTH ANNA - UNIT ~1 6-13a Amendment No. 32,65

ADMINISTRATIVE CONTROLS (Continued) 9

'SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Re0lonal Administrator, Region 11, within the time period specified for each report. These reports shall be submitted pursuant to the requirement of the applicable specification:

a.. Inservice inspection ReWews, Specification 4.0.5, shall be reported within 90 days of completion, i

b. MODERATOR TEMPERATURE COEFFICIENT. Specification 3.1.1.4

c. RADIAT!ON MONITORING INSTRUMENTATION. Specification 3.3.3.1, Table 3.3 6,

' Action 35.

d. SEISMIC INSTRUMENTATION. Specifications 3.3.3.3 and 4.3.3.3.2.

i'

e. METEOROLOGICAL INSTRUMENTATION. Specifcation 3.3.3.4.

f.

Deleted, 5

g. LOOSE PARTS MONITORING SYSTEMS. Specifcation 3.3.3.9.

h. REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY. Speelfcation 3.4.8.

i. OVERPRESSURE PROTECTION SYSTEMS. Specifcation 3.4.9.3.

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EMERGENOY CORE COOUNG SYSTEMS. Specification 3.5.2 and 3.5.3.

k. SETTLEMENT OF CLASS 1 STRUCTURES. Specification 3.7.12.

l.

GROUND WATER LEVEL. SERVICE WATER RESERVOIR. Specification 3.7.13.

m. Deleted,

n. RADIOACTIVE EFFLUENTS. As required by the ODCM.

o. RADIOLOGICAL ENVIRONMENTAL MONITORING. As required by the ODCM.

p. SEALED SOURCE CONTAMINATION. Speellicehon 4.7.11.1.3.

q. REACTOR COOLANT SYSTEM STRUCTURAL INTEGRITY. SpecNicolion 4.4.10. For any i

abnormal degradation of the structural integrity of the reactor vessel or the Reactor-Coolant System pressure boundary detected during the performance of Specification 4.4.10. an initial report shall be submitted within 10 dr:ys after detection and a detailed report submitted within 90 days after the completion of Specification 4.4.10.

NORTH ANNA UNIT 1.

6 21 AmendmentNo. 3.fS.$3.

95.793.130.140

7 ADPINISTRATIVE CONTROLS

r.. CONTAINMENT STRUCTURAL INTEGRITY.Specification 4.6.1.6.

For any abnormal degradation of the containment structure detected during the performance of Specification 4.6.1.6 an initial report shall be submitted within 10 days after the completion of Specification 4.6.1.6.

A final report, which includes (1) a-description of.the condition of the liner plate and concrete. (2) inspection procedure, (3)thetoleranceoncracking,and(4)thecorrectiveactionstaken, shall be submitted within 90 days after the completion of Specifi-cation 4.6.1.6.

l 6.10 RECORD RETENTION 6.10.1 The following records shall be retained for at least five years:

Records and logs of facility operation covering time interval at a.-

each power level, b.

Records and loos of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety, t

ALL REPORTABLE EVENTS anc' Special Reports.

c.

d.

Records of surveillance activities, inspections and calibrations required by these Technical Specifications.

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Records of changes made to Operating Procedures.

e.

f.

Records of radioactive shipments.

9 Records of sealed source leak tests and results.

h.

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

1 Records of the annual audit of the Station Emergency Plan-and implementing procedures.

j.

Records of the annual audit of the Station Security Plan and implementation procedures.

6.10.2 The following. records shall be retained for the duration of the-p Facility Operating License:

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PORTH ANNA - UNIT 1 6-22 Amendment No. 3,$8,f3.78,103 L

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UNITED STATES NUCLEAR REGULATORY COMMISSION a

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VIRGINIA ELECTRIC AND POWER COMPANY l

OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-339

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NORTH ANNA POWER STATION UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.123 License No. NPF-7 1.

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

A.

The application for amendment by Virginia Electric and Power Company, l

etal.,(thelicensee)datedJune 26, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954,.

j as-amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; I,

B.

The facility will operate in conformity with the application, the provisions of-the Act, and the rules and regulations of the Comission; c

C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the common l

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

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

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.i 2.

Accordingly, license condition 2.C.(23) is hereby added to Facility Operating License NPF-7 to read as follows:

(23) Fire protection VEPC0 shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility and as approved in the SER dated February 1979 subject to the following provision:

The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

3.

In addition, the license is amended by changes to the Technical Speci-fications 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 Technica1' Specifications contained in Appendices A and B, as revised through. Amendment No.123. are hereby incorporated in the license. The licensee shall operate the facility in accordance with tne Technical Specifications.

4 This license amendment is effective as of the date of issuance and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION

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

Attachment:

Changes to the Technical

' Specifications

[

Date of Issuance: September 13, 1990

y ATTACHMENT TO LICENSE AMENDMENT NO.123

.T0 FACILITY OPERATING LICENSE NO. NPF-7 4

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 amendwent number and contain vertical lines indicating the area of change.

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

Page IV VIII XIII 3/4 3-49 through 3/4 3-50a (deleted) 3/4 7-59 through 3/4 7 70 (deleted)

B 3/4 3-3 B 3/4 7-9 B 3/4 7-10 6-la 6-8 6 14 6-21 i

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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE' 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 Axial Flux Difference..................................

3/4 2-1 3/4.2.2 Be a t Flux Ho t r'ha nn e l Fa c t o r...........................

3/4 2-5 3/4.2.3 Nuclear Enthalpy Rot Channel Factor....................

3/4 2-9 3/4.2.4 Quadrant Power Tilt Ratio..............................

3/4 2-12 3/4.2.5 DNB Parameters.........................................

3/4 2-15 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION....................

3/4 3-1 3/4.3.2 ENGINEERED SATETY FEATURE ACTUATION SYSTEM INSTRUMENTATION........................................

3/4 3 3/4.3.3 -MONITORING INSTRUMENTATION Radiation Monitoring...................................

3/4 3-38 Movable Incore Detectors...............................

3/4 3-42 Auxiliary Shutdown Panel Monitoring Instrumentation.....

3/4 3-43 Accident Monitoring Instrumentation....................

~3/4 3-46 Explosive Gas Moni toring Instrumentation...............

3/4 3-52 i

l 3/4.4 REACTOR C00LANT SYSTEM

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3 /4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION Startup and Power Operation...........................

-3/4 4-1 Hot Standby...........................................

3/4 4-2 Shutdown..............................................

3/4 4-0 Isolated Loop.........................................

3/4 4-4 Isolated Loop Startup.................................

3/4 4-5 NORTH ANNA - UNIT 2 IV Amendment No. 8/f.pf, g,

123, 1

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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.7 PLANT SYSTEMS 4

3/4.7.1 TURBINE CYCLE Safety Valves.......................................... 3/4 7-1 l

Auxil i a ry Feedwa ter Sys tem............................. 3/4 7 Emergency Conoensate Storage Tank...................... 3/4 7-7 A c t i v i ty............................................... 3 / 4 7-8 Main Steam Trip Valves................................. 3/4 7-10 Steam Turbi ne As s embly.................................. 3/4 7-11 Overspeed Protection................................... 3/4 7-12 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE !, IMITATION........ 3/4 7-13 3/4.7.3 COMPONENT COOLING WATER SUBSYSTEM....................... 3/4 7-14 3/4.7.4 SERVICE WATEP. SYSTEM................................... 3/4 7-15 3/4.7.5 ULTIMATE HEAT sit!K..................................... 3/4 7-16 3/4.7.6 FLOOD PROTECTION....................................... 3/4.7-17 3/4.7.7 CONTROL ROOM _ EMERGENCY HABITABILITY SYSTEMS............ 3/4 7-18 3/4.7.8 SAFEGUARDS AREA VENTILATION SYSTEM..................... 3/4 7-21 3/4.7.9 RESIDUAL HEAT REMOVAL' SYSTEM RHR - Ope ra ti ng........................................ 3/4 7 l RHR - Shutdown......................................... 3/4 7-24 1

3/4.7.10 SNUBBERS............................................... 3/4 7-25 l

l 3/4.7.11 SEALED SOURCE CONTAMINATION.............................-3/4 7-51 3/4.7.12 SETTLEMENT OF CLASS 1 STRUCTURES....................... 3/4 7-53 L

3/4.7.13 GROUNDWATER LEVEL-SERVICE WATER RESERVOIR.............. 3/4 7-57 o

NORTH ANNA - UNIT 2 VII l

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l INDEX i

1.IMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS

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3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A. C. SOURCES O p e r a t i n g.............................................

3/ 4 8-1 S h u t d ow n..............................................

3/ 4 8-10 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A. C. Distribution - Operating........................ 3/4 8-11 A. C. Di s tri bution - Shutdown.........................

3/4 6-12 D. C. Distribution - Operating........................ 3/4 8-13 D. C. Distribution - Shutdown.........................

3/4 8-15 Containment Penetration Conductor Overcurrent Protecti ve Devi ces.................................... 3/4 8-16 Motor Operated Valves Thermal Overload Protection a nd/o r Bypa s s Devi ces.................................

3/4 8-21 E

l' NORTH ANNA - UNIT 2 VIII Amendment No. 85.123, l.

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H2EE BASES IEEN ME S/4.7 PLANT SYSTEMS 1

3/4.7.1 TU RBIN E C YC LE................................. -......................................

3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE UMITATION...B 3/4 7 4 3/4.7.3 COMPONENT COOUNG WATER SUESYSTEM...........

B 3/4 7 4 3/4.7.4 SERVIC E WATER SYSTEM...................................................... B 3/4 7 4 3/4.7.5 ULTIMAT E HEAT S I NK......................................................................

B 3/4 7 5 3/4.7.6 FLOOD PROT E CTION...................................................................B 3/4 7 5 3/4.7.7 CONTPOL ROOM EMERGENCY HABITABILITY................................B 3/4 7 5 3/4.7.8 SAFEGUARDS AREA VENTILATION SYSTEM.............................

B 3/4 7 5 3/4.7.9 RESIDUAL H EAT REMOVAL SYSTEMS........................

B 3/4 7 6 3/4.7.10 SNUBBER5...................................................................................

B 3/4 7 6 3/4.7.11 SEALED SOURCE CONTAMINATION................................... B 3/4 7 7 3/4.7.12 SETTLEMENT OF CLASS 1 STRUCTURES.............................. B 3/4 7 7 3/4.7.13 GROUNDWATER LEVEL. SERVICE WATER RESERVOIR............

B 3/4 7 9

.o 3/4 8 ELECTRICAL POWER SYSTEMS 3/4.8.1 and 3/4.8.2 A.C. ANDD.C. POWER SOURCES AND D I ST RI B t rTI ON...................................................................... B 3/4 8 1 NORTH ANNA UNIT 2 Xill Amendment No.123,

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INDEX i

' BASES' SECTION PAGE

-3/4.9 REFUELING' OPERATIONS 3/4.9.1 BORON CONCENTRATION.......................................

B 3/4 9-1 3/4.9.2 INSTRUMENTATION...........................................

B 3/4 9-1 j

L 3/4.9.3 DECAY TIME................................................

B 3/4 9-1 3/4.9.4 ~ CONTAINMENT BUILDING PENETRATIONS.........................

B 3/4 9-1 3/4.W.5 COMMUNICATIONS............................................

B 3/4 9-1 i

l 3/4.9.6 MANIPULATOR CRANE OPERABILITY.............................

B 3/4 9-2' 3/4.9.7-CRANE TRAVEL - SPENT FUEL PIT.............................

B 3/4 9-2

-3/4.9.8-RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION.............

B 3/4 9-2 3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM............

B 3/4 9-2 3/4.9.10 and 3/4.9.11 WATER LEVEL-REACTOR VESSEL AND SPENT FUEL PIT.................................................

B 3/4 9-3

-3/4.9.12 FUEL BUILOING VENTILATION SYSTEM..........................

B 3/4 9-3

' 3 /4.~ 10 SPECIAL TEST EXCEPTIONS.

s 3/4.10.1 SHUTDOWN MARGIN...........................................

B 3/4 10-1

3/4.10.2 ' GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION 1

LIMITS....................................................

B 3/4 10-1 1

3/4.10.3J PHYSICS ~ TESTS.............................................

B 3/4 10-1 l-

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3/4.10.4 REACTOR COOLANT.L00PS.....................................

B 3/410-1 1

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-3/4.10.5: POSITION INDICATOR CHANNELS - SHUTDOWN....................

S 3/4 10 l li I'

i NORTH ANNA - UNIT 2 XIV l

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l NORTH ANNA UNIT 2 B 3/4 3 3 Amendment No. 5A.123, I

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l BASES

- 1'd 7.13 GROUNDWATER LEVEL RERVICE WATER RERERVotR A program to monitor groundwater levels in the area of the service water reservoir has been established to ensure that the integrity of the service water reservoir embankments and l

pumphouse is maintained.

Groundwater threshold levels have been established based on historical groundwater data available in 1977. These levels are sufficiently conservative to ensure that the service water reservoir and pumphouse will perform their intended function. An engineering evaluation will be performed if these threshold values are exceeded, to determine if there is any substantive cause to pelieve that any aspect of the service water reservoir, dike or pumphouse will not perform its intended func* ion. A conclusion to this effect, and the appropriate corrective actions to be performed, will be reported to the Commission.

The groundwater threshold levels are periodically reviewed to determine whether a changing groundwater environment warrants a change in threshold levels.

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NORTH ANNA UNIT 2 B 3/4 7 9 -

Amendment No. -123, l

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. NORTH ANNA UNIT 2 83/4710 Amendment c.123,

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,ADMINISTRATIVECONTROLS 1,

-e.

The management position responsible for health physics shall have direct access to that onsite individual having responsibility for overall facility management.

Health physics personnel shall have the authority to cease any work activity when worker safety is jeo unnecessary personnel radiation exposures. pardized or in the event of FACILITY STAFF 6.2.2 The Facility organization shall be as shown in the UFSAR.

a.

Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.21 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 1, 2, 3 or 4, at least one licensed Senior Reactor Operator shall be in the Control Room.

c.

A health physics techniciene shall be onsite when fuel is in the reactor.

d.

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

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1. The health physics technician and Fire Brigade composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order I

to accommodate unexpected absence provided immediate action'is taken to fill the required positions.

NORTH ANNA - UNIT 2 6-la Amendment No. 77,67,73, (f.

123,

~f ADMfNISTRAT8VE CONTROLS MEETING FREQUENCY 6.5.1.4 The $NSOC shall meet at least once per calendar month and as convened by the; SNSOC Chairman or his designated alternate, OUORUM i

6.5.1.5 A quorum of the SNSOC consists of the Chairman or. Vice-Chairman and two members including alternates.

RESPONSIBILITIES 6.5.1.6 The SNSOC shall be responsible for:

Review of 1) all procedures required by Specifications 6.8.1, 6.8.2 a.

and 6.8.3 and changes thereto, 2) all programs required by Specifica-tion 6.8.4-and changes thereto, 3) any other proposed procedures or changes thereto as determined by the Station Manager to affect nuclear safety, l

Review of all proposed tests and experiments that. affect nuclear b.

safety, Review of all proposed etenges or modifications to plant systems c.

or equipment that affect aclear safety.

t d.

Review of.all proposed changes to-Appendix "A" Technical jg Specifications and Appendix "B" Environmental Frotection Plan.

Recommended changes shall be submitted to the Station Manager, Investigation of all violations of the Technical Specifications e.

including the preparation and forwarding of reports covering evalua-tion and recompendations to prevent recurrence to the Vice President-Nuclear and the offsite management position responsible for independent / operational event review.

f.

Review of all REPORTABLE EVENTS and Special Reports.

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Review of facility operatio's to detect potential nuclear safety,

-g.

n i

hazards.

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

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i.

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

j.

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

NORTH ANNA - UNIT 2 6-7 Amendment No. II, (? $7, BC L

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ADMINISTRATIVE CONTROLS

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,l K. Review 'of every unplanned onsite release of radioactive material to the environs including the-preparation of reports covering evaluation, recommendatione AM disposition of the corrective action to prevent recurrence and the forwarding of these reports to the Vice President. Nuclear and the offsite management position responsible for independent / operational event review.

1.

Review changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATONMANUAL

m. Review of the Fire Prc:ection Program d implementing procedures and shall submit

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recommended changes to the Station Manager.

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-l 6.5.1.7 The SNSOC shal:

a. Provide written approval or disapproval of items considered under 6.5.1.6(a) through (c) above, SNSOC approval shall be certified in writing by an Assistant Station

Manager,

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 unreveiwod safety question, Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vice President Nuclear and the c.

s offsite management position responsible for independent / operational event review of' disagreement between the SNSOC and the Station Managen twever, the Station Manager,shall have ' responsibility for resolution of such disagreements pursuant to li 6.1.1 above.

HDMKt 6.5.1.8 The SNSOC shall maintain written minutes of each meeting and copies shall be provided to the Station Manager, Vice President. Nuclear and the offsite management position responsible l

for independent / operational event review, p

812 INDEPENDENTOPERATIONAL EVENT REVIEW nopR) GRollp FLNCmON 6.5.2.1 The IOER Group shall function to provide independent review of designated activities in L

the areas of:

l-L a.

Nuclear power plant operations L

b.

Nuclear engineering c.

Chemistry and radiochemistry d.

Metallurgy e.

Instrumentation and control f.

Radiological safety g.

Mechanical and electrical engineering h.

Administrative controls and quality assurance practices 1.

.Other appropriate fields associated with the unique characteristics of the nuclear power plant NORTH ANNA -UNIT 2 68 Amendment No. 17.37.57.56.123

' ADMINISTRATIVE CONTROLS Surveillance and test actMties of safety related equipment.

c.

d.

Security Plan implementation.

e.

Emergency Plan implementation.

A f.

Fire Protection Program implementation.

g.

PROCESS CONTROL PROGRAM implementagon.

h.

OFFSITE DOSE CALCULATION MANUAL implementadon.

I.

Quality Assurance Program for effluent ano environmental monitoring, using the guidance in Regulatory Guide 1.21 Revision 1. June 1974 and Regulatory Guide 4.1,. Revision 1, April 1975.

6.8.2' Each procedure of 6.8.1 above, except 6.8.1.d. 6.8.1.e. and 6.8.1.1 and changes the shall be reviewed and approved by the SNSOC prior to ' p rf tion and reviewed periodicall s

as set forth in administrative proced'Jres. Procedure of 8.8.1.d. 4.4.1.e, and 6.8.1.1 shall be reviewed and approved as per certified in writing by an Assistant Station Manager.6.5.1.6.1, 6.5.1.6.), and 6.5.1.81 6.8.3 Temporary changes to procedures of 6.8.1 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 Uonnse on tne unit affecid.

c. The change is documented,' reviewed, and approved by the SNSOC within 14 days of implementation. SNSOC approval shall be certified in writing by an Assistant Station Manager.

6.8.4 The following programs shall be established, implemented, and maintained:

a. Primary Coolant SovI;;gs Outelde containment A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious t:ansient or accident to as low as practical levels. The systems include the recirculation spray, safety in}ection, chemical and volume control, gas stripper, and hydrogen recombiners.

The program shall include the following:

(i) Preventive maintenance and periodic visual inspection requirements, and (11) Integrated leak test requirements for each system at refueling cycle intervals or less, NORTH ANNA - UNIT 2 6-14 t

Amendment No. U,67.123,

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ADMINISTRATIVE CONTROLS

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6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTA8LE EVENTS:

The Comission shall be notified and a report submitted a.

pursuant to the requirements of Section 50.73 to 10 CFR Part 50,'

and b.

Each REPORTABLE EVENT shall be reviewed by the $NSOC and the results of this review shall be submitted to the Vice President.

Nuclear and the offsite management position responsible for 10ER.

I 6.7 SAFETY LIMIT VIOLATION l16.7.1 The following actions shall be taken in the event a Safety Limit is l

ll lviolated:

ill a.

The facility shall be placed in at least HOT STANDBY within

{l one hour.

I b.

The NRC Operations Center shall be notified by telephone as'soon as possible and in all cases within one hour. The Vice President-Nuclear and the offsite management position responsible for 10ER shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

c.

A Safety Limit Violation Report shall be prepared. The report l'l shall be reviewed by the SNSOC.

This. report shall describe (1) applicable circumstances preceding the violation, (2) effects jl of the violation upon facility components, systems or structures, and. (3) corrective action taken to prevent r2currence.-

d.

The Safety Limit Violation Report shall.be submitted tL she Comission, the Vice President-Nuclear and the offsite management position. responsible. for IDER within 14 Atys of the. violation.

6.8 PROCEDURES AND PROGP.AMS

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

The applicable procedures recomended in Appendix "A" of Regulatory a.

Guide 133. Revision 2 February 1978.

b.

Refueling operations.

NORTH ANNA - UNIT 2 6-13 Amendment No. 77, Ali7, 86

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= ADMINISTRATIVE CONTROLS SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the _ Regional Administrator, Region 11, within the time period specified for each report. These reports shall be submitted pursuant to the requirement of the applicable specification:

a. Inservice inspection Reviews, Specification 4.0.5, shall be reported within 90 days of completion.

b. MODERATOR TEMPERATURE COEFFICIENT. Specification 3.1.1.4.

c.

Deleted, d.

RADIATION MONITORING INSTRUMENTATION. Specification 3.3.3.1, TABLE 3.3 6 Action 35.

e. REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY. Specifcation 3.4.8.

f.

OVERPRESSURE PROTECTION SYSTEMS. Specircation 3.4.9.3.

g. EMERGENCY CORE COOLING S YSTEMS. Specifcation 3.5.2 and 3.5.3 h.

SETTLEMENT OF CLASS 1 STF JCTURES. Specification 3,7.12.

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i. GROUND WATER LEVEL SERVICE WATER RESERVOIR. Specifcation 3.7.13.

J.

Deleted.

l k.

Deleted.

I.

RADIOACTIVE EFFLUENTS. As required by the ODCM.

m. RADIOLOGICAL ENVIRONMENTAL MONITORING. As required by the ODCM.

n. SEALED SOURCE CONTAMINATION. Specification 4.7.11.1.3.

o. REACTOR COOLANT SYSTEM STRUCTURAL INTEGRITY. Specircation 4.4.10. For any abnormal degradation of the structural integrity of the reactor vessel or the Reactor Coolant System pressure boundary detected durin0 the performance of. Specification 4.4.10, an initial report shall be submitted within 10 days after detection and a -

detailed report submitted within 90 days after the completion of Specification 4.4.10.

p. CONTAINMENT STRUCTURAL INTEGRITY. Specification 4.6.1.6. For any abnormal degradation of the containment structure detected during the performance of Specification 4.6.1.6, an initial report shall be submitted within 10 days after completion-of Specification 4.6.1.6.. A final report, which includes (1) a description of the condition of the liner plate and concrete, (2) inspection procedure, (3) the tolerance on cracking and (4) the corrective actions taken, shall be submitted within 90 days af ter the completion of Specification 4.6.1.6.

NORTH ANNA UNIT 2 6 21 Amendment No. 37,(7,SJ, 99 AAA,123,

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