ML20070L560

Proposed Tech Specs Re Completion of License Condition 2.c(21)(e) Re Radioisotopic & Chemical Analysis by No Later than 830401

ML20070L560
Person / Time
Site:	North Anna
Issue date:	12/29/1982
From:	VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML20070L552	List: ML20070L550 ML20070L560
References
NUDOCS 8301030182
Download: ML20070L560 (6)

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ATTACHMENT 1 PROPOSED OPERATING LICENSE AMENDMENT D'01030182 821229 PDP ADOCK 05000339 P PDR

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9 (c) Reactor Coolant System Vents (Section 22.2 Item 11.B.1)

VEFC0 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 Shielding (Section 22.3 Item II.B.2)

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

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

VEPCO shall complete corrective actions needed to provide the capabi-lity to promptly obtain and perform radioisotopic ar.d 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 April 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-

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lief and safety valves under expected operating conditions for design basis transients and accidents no later than July 1, 1982.

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

VEPC0 shall implement the modification to upgrade the safety-grade indications of AFW flow from semi-vital bus power to vital bus power no later than January 1, 1981.

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

VEPCO 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 recombiner piping to remote manual actua*<'n no later than the implementation schedule of NUREG-0737.

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

VEPC0 shall install and demonstrate the operability of instruments for continuous indication in the control room of the following variables.

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

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• O ATTACHMENT 2 DISCUSSION OF PROPOSED OPERATING LICENSE AMENDMENT l

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DISCUSSIP" CF PROPOSED OPERATING LICENSE AMENDMENT North 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 atmosphere samples under degraded core conditions without excessive exposure at the first outage of sufficient duration but no later than January 1, 1983."

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

The Containment Atmosphere Sampling System has all sampling and analysis equipment installed. A containment air sample has successfully been drawn into the system and has successfully been analyzed using the chemical analysis equipment.

The Reactor Coolant Sampling System has been installed and is undergoing final startup testing. A reactor coolant sample has not been successfully analyzed due to a problem in the chemical analysis equipment, specifically, a damaged pH probe. An RCS sample has not been drawn prior to repairing the pH probe since doing so would contaminate the system and complicate equipment repair.

The proposed schedule extension is necessary to allow time to repair the analysis equipment problem. The proposed extension does allow some time for additional unforeseen problems.

Interim sampling procedures that are required by the short-term TMI requirements will be in effect until the entire Post-Accident Sampling System is fully 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 the operability of the Post-Accident Sampling System. Interim sampling procedures are in effect.

The possibility of a different type of accident or malfunction than was previously evaluated in the FSAR has not been created by the delay in operability.

The margin of safety as described in the BASIS section of any part of the Technical Specifications is not reduced because of the delay in completing the Post-Accident Sampling System. This delay will in no way affect the safe operation of the plant. Interim sampling procedures will remain in effect until the Post-Accident Sampling System is fully operable.

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COMMONWEALTH OF VIRGINIA )

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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 Vice President-Nuclear Operations, 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 t.he best of his knowledge and belief.

Acknowledged before me this A ?c4day ofAA.A- d +

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My Commission expires: cR 2 6 , 19 $? s' .

b. M *A Notary Public (SEAL)

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