ML20126D879

Amends 169 & 148 to Licenses NPF-4 & NPF-7,respectively, Revising Current NA-1&2 TS Pertaining to Monitoring Program for Secondary Water Chemistry

ML20126D879
Person / Time
Site:	North Anna
Issue date:	12/09/1992
From:	Berkow H Office of Nuclear Reactor Regulation
To:
Shared Package
ML20126D882	List: ML20126D879 ML20126D903
References
NUDOCS 9212280202
Download: ML20126D879 (10)

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VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERAlIVE DOCKET NO. 50-338 NORTH ANNA POWER STATION. UNIT N0, 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 169 License No. NPF-4 1.

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

A.

The application for amendment by Virginia Electric and Power Company et al., (the licensee) dated September 4, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Connission; C.

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

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

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

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. 2.

Accordingly, the license is amended by changes to the Technical Speci-fications 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. 169, are hereby incorporated in the license.

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

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION rbert N. Berk w, Director roject Directorate 11-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: December 9, 1992 i

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ATTACHMENT TO LICENSE AMENDMENT NO.160 TO FACILITY 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 page is identified by amendment number and contains vertical lines indicating the area of change.

The corresponding overleaf page is also provided to maintain document completeness.

Remove Paaes Insert Paaes 6-13 (no changes) 6-13 (no changes) 6-13a 6-13a 1

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ADMIN!STRAT!VE CONTROLS c.

Surveillance and test activities of safety related equipment, d.

Security Plan implementation.

e.

Emergency Plan implementation.

f.

Fire Protection Program implementation, 9

FR0 CESS CONTROL PROGRAM implementation, h.

OFF5ITE DOSE CALCULATION MANUAL implementation.

i.

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 s'ive, except 6.8.1.d. 6.8.1.e; and 6.8.1.f and l

Changes thereto, shall be reviewed and 'spproved by the $N50C prior to implemen.

tation and reviewed periodicelly as set, forth in administrative procedures.

Ptocedure of 6.8.1.d 6.8.1.e. and 6.8.1.f shall be reviewed s'ad approved as l

pe r 6.5.1. 6.1, 6. 5.1. 6.j, a nd 615.1. 6.m.

$N50C 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 original procedure is not altered.

b.

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

The change is documented, reviewed, and approved by the SNSOC within 14 days of implementation. $N500 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 (ii) Integrated leak test requirements for each system at refueling cycle intervals or less.

I NORTH ANNA - UNIT 1 6 13 Amendment No. 5,75,32,5412,140, SEP 131990

ADMINISTRATlVE CONTROLS b, in Plant Radiation Monfterina A program which will ensure the capability to accurately determine the alttome iodine concentration in vital areas under accident conditions. This program shall include the following:

(l)

Training of personnel, (ii)

Procedures for monitoring, and (lil)

Provisions for maintenance of sampling and analysis equipment.

C.

Secondarv Water Chemittnr A program for monitoring of secondary water chemistry to inhibit steam generator tube degradation. This program shallinclude:

(i)

Identification of a sampling schedule for the critical variables and control points for these variables, (ii)

Identification of the procedures used to measure the values of the crit' cal

vanables, (iii)

Identification of process sampling points,which shallinefade monitoring the discharge of the condensate pumps for evidence of condenser inleakage, (iv)

Procedures for the recording and rnanagement of data, (v)

Procedures defining corrective actions for all control point chemistry conditions, and (vi)

A procedure identifying (a) the authority responsible for the interpretation of the data, and (b) the sequence and timing of administrative events required to initiate corrective action.

d.

Pont Accident Samolina A program which will ensur6 the capability to obtain and analyze reactor coolant, radioactive lodines and particulates in plant gaseous ettluents, and containment atmosphere samples under accident conditions. The program shallinclude the following:

(i)

Training of personnel, (ii)

Procedures for sampling and analysis, (iii)

Provisions for maintenance of sampling and analysis equipment.

NORTH ANNA UNIT 1 613a Amendment No.M,-M.169

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VIRGINIA ELECTRIC Ap0 POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO, 50-339 HQRTH ANNA POWER STATION. UNIT N0. 2 AMENDMENT 10 FACIL'iTY OPERATING tICENSE Amendment No.148 License No. NPF-7 1.

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

A.

The application for amendment by Virginia Electric and Power Company et al., (the licensee) dated Se)tember 4, 1992, complies with the standards and requirements of tie Atomic Energy Act of 1954, as amended (the Act), arj 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 (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 conducte" in compliance with the Commission's regulations; D.

The ir aance 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.

4 2.

Accordingly, the license is amended by changes to the Technical Speci-fications as indici.ted 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 Specificatio.nl The Technical Specifications contained in Appendices A and B, at revised through Amendment No.148

, are hereby incorporated in the license.

The licensee shall oparate the facility in accordance with the Technical Specificati, -

3.

Tnis license amendment is effective 4s of its date of issuance and shall be implemented within 30 days.

FOR T NUCLEAR REGULATORY COMMISSION H bert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: December 9, 1992

ATTACHMENT TO LICENSE AMENDMEr#T NO.148 TO FACILITY OPERATING LICENSE NO. NPF-7 QDCKET NO. 50-339-Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated.

The revised page is identified by amendment-number and contains vertical lines indicating the area of change.

The corresponding overleaf page is also provided to maintain document completeness.

Remove Paaes Insert Paaes 6-14a 6-14a 6-14b (no changes) 6-14b (no changes)

ADMINISTRATIVE CONTROLS b.

In Plant Radiation Menderino A program which will ensure the capability to accurately determine the alttome iodine concentration in vital areas under accident conditions. This program shall include the following:

(i)

Training of personnel, (ii)

Procedures for monitoring, and (iii)

Provisions for maintenance of sampling and analysis equipment.

c. Secondarv Water Chemistrv A program for monitoring of secondary water chemistry to inhibit steam generator tube degradation. This program shallinclude:

(i)

Identification oi a sampling schedule for the critical variables and control points for these variables, (ii)

Identification of the procedures used to measure the values of the critical,

variab!es, (iii)

Identification of process sampling points, which shallinclude monitoring the discharge of the condensate pumps for evidence of condenser inteakage, (iv)

Procedures for the recording and management of data, (v)

Procedures defining corrective actions for all control point chemistry conddions, and (vi)

A procedure identifying (a) the authority responsible for the interpretation of the data, and (b) the sequenc3 and timing of administrative events required to initiate corrective action.

d.

Post-Accident Samolino A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atnusphere samples under accident conditions. The program shallinclude the following:

(i)

Training of personnel, (ii)

Procedures for sampling and analysis, (iii)

Provisions for maintenance of sampling and analysis equipment.

NORTH ANNA UNIT 2 6-14a Amendment No.56,148 I

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i ACMINISTRATiVE CCNTACLS e.

Pa&2ctive Cfffuent Centrols o'eeram y

A program snall be Drovioed conforming witn 10 CFR 50.36a for the control of racioactive effluents as low as reasonaoty achievable.radioacuve efflueitts The program (1) snatt os contained in tne OOCM, (2) snail be implemented by operating procedures, and (3) snali inctuce remedial actions to be taken whenever the program limits are excesced The program snallinclude the following elements:

1 ) Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the metnodology in the OCCM, 2 ) Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to to CFR Part 20, Appencix B.

Table 11, Column 2.

3 ) Monitonng, sampling, and analysis of racioactive liquid and gaseous effluents in accordance with 10 CFR 20.106 and with the metnodology and parameters in the 00CM.

4 ) Limitations on the annual and cuarterty doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from eacn

, unit to UNRESTRICTED AREAS conforming to Appendix ! to 10 CFR Part 50, 5 ) Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance witn the metnodology and parameters in the CDCM at least every 31

days, 6 ) Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactuity when the projected doses in a 31 day pened would axceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix l to 10 CFR Part 50, 7 ) Limitations on the dose rate resulting from radioactive material released in gaseous ettluents to areas beyond the SITE BOUNDARY conforming to the doses associated with 10 CFR Part 20, Appendix S. Table ll, Column 1 NORTH ANNA UNIT 2 6-14b AmendmentNo J7,114 Jtil.191990

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