ML20079F549

Application for Amend to License NPF-7 Extending Completion Deadline for License Condition 2.C(21)(e) Re Reactor Coolant & Containment Atmosphere Sampling Until 830101

ML20079F549
Person / Time
Site:	North Anna
Issue date:	06/04/1982
From:	Leasburg R VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	Clark R, Harold Denton Office of Nuclear Reactor Regulation
References
322, NUDOCS 8206080061
Download: ML20079F549 (7)

Text

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VIRGINIA ELECTRIC AND PowEn COMPANY HrcuwoNn, VruoINIA 23261 R.11. Laanno mo June 4, 1982 Vace Pomosomm7 NecLeam oramarious Mr. Harold R. Denton, Director Serial No. 322 Office of Nuclear Reactor Regulation N0/JHL:acm l

Attn:

Mr. Robert A. Clark, Chief Docket No. 50-339 Operating Reactors Branch No. 3 License No. NPF-7 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Gentlemen:

AMENDMENT TO OPERATING LICENSE NPF-7 NORTH ANNA POWER STATION UNIT NO. 2 PROPOSED OPERATING LICENSE AMENDMENT I

l Pursuant to 10 CFR 50.90, the Virginia Electric and Power Company requests an amendment to operating License NPF-7 for North Anna Power Station Unit No. 2.

The proposed change to the Operating License is enclosed.

License Condition 2.C(21)(e) of the North Anna Unit 2 Operating License

states, "VEPCO shall complete corrective actions need to provide the l

capability to promptly obtain and perform radioisotopic and chenical analysis of reactor coolant and containment atmosphere samples under degraded core conditions without excessive exposure by no later than July 1,

1982."

The proposed change is to complete License Condition 2.C(21)(e) by no later than January 1, 1983.

The schedule extension is required to accomodate material delivery delays in receipt of the supply line heat tracing components.

The proposed amendment is provided in Attachment 1.

A discussion of the proposed change is provided in Attachment 2.

This request has been reviewed and approved by the Station Nuclear Safety and Operating Committee and the Safety Evaluation and Control staff.

It has been determined that this request does not involve an unreviewed safety question as defined in 10 CFR 50.59.

We have evaluated this request in accordance with the criteria in 10 CFR 170.22.

Since this request involves a safety issue which the Staff should be able to determine does not pose a significant hazard consideration for Unit 2, a Class III license amendment fee is required for Unit 2.

Accordingly, a voucher check in the amount of $4000.00 is enclosed in payment of the required fees.

j Very truly yours, I/

l.

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wlclck:

R. H. Leasburg wX Yooo.co 8206080061 820604 PDR ADOCK 05000339 P

PDR

Vauorwi4 Ettermic awn Powra Couraxy to Harold R. Denton Attachments:

1.

Proposed Operating License Amendment 2.

Discussion of Proposed Operating License Amendment 3.

Voucher Check No. 28884 for $4000.00 cc:

Mr. James P. O'Reilly Regional Administrator Region II 1

1

s COMMONWEALTH OF VIRGINIA )

)

CITY OF RICHMOND

)

The foregoing document was acknowledged before me, in and for the City and Commonwealth aforesaid, today by W.

L.

Stewart, who is Manager-Nuclear Operations and Maintenance, of the Virginia Electric and Power Company. He is duly authorized to execute and file the foregoing document in behalf of that Company, and the. statements in the document are true to the best of his knowledge and belief.

Acknowledged before me this Y

day of h-

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Hy Commission expires:

-:R - A4 19 P[.

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Notary Public i

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(SEAL)

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ATTACHMENT 1 PROPOSED OPERATING LICENSE AMENDMENT D

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, (c) Heactor Ccolant System Vents (Section 22.2 Item II.B.1)

VEPCO shall submit procedural guidelines and analytical bases for the reactor coolant system vents.

The reactor coolant system vents shall be installed no later than the implementation schedule of NUREG-0737.

(d) Plant Shi'elding (Section 22.3 Item II.B.2)

VEPCO shall complete modifications to assure adequate access to vital areas and protection of safety equipment following an accident result-ing in a degraded core no later than the implementation schedule of dUREC-0737.

(e) Post-Accident Sampling (Section 22.3 Item II.B.3)

VEPC0 shall complete corrective actions needed to provide the capabi-lity to promptly obtain and perform radioisotopic and chemical analysis of reactor coolant and containment atmosphere samples under degraded core conditions without excessive exposure at the first outage of sufficient duration but no later than January 1, 1983.

(f) Relief and Safety Valve Test Requirements (Section 22.3 Item II.D.1)

VEPCO shall complete tests to qualify the reactor coolant system re-lief and safety valves under expected operating conditions for design basis transients and accidents no later than July 1, 1982.

g (g) Auxiliary Feedwater Initiation and Indication (Section 22.3 Item II.E.1.2)

VEPCO shall implement the modification to upgrade the safetygrade indications of AFW flow from semi-vital bus power to vital bus power f

no later than January 1, 1981.

(h) Containment Dedicated Penetrations (Section 22.3 Item II.E.4.1)

VEPC0 shall install redundant remote actuated valves in series to isolate the containment vacuum pumps from the combustible gas control system.

VEPCO shall also convert the manual valves in the hydrogen r

recombiner piping to remote manual actuation no later than the implementation schedule of NUREG-0737.

(i) Additional Accident Monitoring Instrumentation (Section 22.3 Item II.F.1)

VEPCO shall install and demonstrate the operability of instrumcnts for continuous indication in the control room of the following variables.

Each item shall be completed by the specified date in the condition:

0 ATTACHMENT 2 DISCUSSION OF PROPOSED OPERATING LICENSE AMENDMENT

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DISCUSSION OF FROPOSED OPERATING LICENSE AMENDMENT horth Anna Unit 2 License Condition 2.C(21)(e) states, "VEPCO shall complete corrective actions needed to provide the capability to promptly obtain and perform radioisotopic and chemical analysis of reactor coolant and containment atnosphere samples under degraded core conditions without excessive exposure at the first outage of sufficient duration but no later than July 1, 1982."

The proposed amendment for Unit 2 License Condition 2.C(21)(e) is to complete the Post-Accident Sampling System no later than January 1, 1983.

The Reactor Coolant Sampling System will be operational by July 1, 1982. The Reactor Coolant Sampling System is installed and is undergoing final startup testing.

Interim sampling procedures that are required by the short-tern TMI requirements will be in effect until this system is operational.

The Containment Atmosphere Sampling Sjstem has all sampling and analysis equipment installed and it is undergoing startup testing.

The schedule extension, to January 1, 1983, is due to delayn in receipt of the supply line heat tracing components.

The interim sampling procedures required by the short-term TMI requirements will remain in effect until the permanent Containment Atmosphere Sampling System is operational.

The probability of occurrence or the consequences of a malfunction of equipment important to safety and previously evaluated in the FSAR is not increased because of a delay in installing the Post-Accident Containment Atmosphere Sampling System.

Interim sampling 1.rocedures will remain in effect until the entire Post-Accident Sampling System is completed.

The Post-Accident Sampling System is being installed with applicable administrative controls.

The possibility of a different type of accident or malfunction than was previously evaluated in the FSAP. has not been created by the installation delay. The installation of the Post-Accident Sampling System is in accordance with applicable design requirements of the FSAR.

The margin of safety as described in the BASIS section of any part of the Technical Specifications is not reduced because the delay in completing the Post-Accident Sampling System will in no way affect the safe operation of the plant.

Interim sampling procedures will renain in effect until the Post-Accident Sampling System is fully operable.

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