ML20198P998

Special Rept 2-SR-86-014:on 860421,discovered That Unit Potentially Exceeded Time Limits for Action Statement 3 of Tech Spec 3.3.1.Tech Spec 3.0.3 Exited 15 Minutes After Entry & Event Terminated

ML20198P998
Person / Time
Site:	Palo Verde
Issue date:	05/21/1986
From:	Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
2-SR-86-014, 2-SR-86-14, ANPP-36658-EEVB, NUDOCS 8606090037
Download: ML20198P998 (2)

Text

- 3 Arizona Nuclear Power Project P o. BOX 52034

• PHOENIX, Am2oNA 85072-2034 May 21, 1986 ANPP-36658-EEVB/PGN/98.05 Mr. John B. Martin, Regional Administrator Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Region V 1450 Maria Lane, Suite 210 Walnut Creek, CA 94596-5368

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

Unit 2 Docket No. STN 50-529 (License NPF-51)

Special Report SR-86-014 File: 86-020-404

Dear Mr. Martin:

Attached please find a Special Report (2-SR-86-014) voluntarily submitted, for informational purposes only. This report discusses an event that was reported to the NRC Operations Center, but was later determined to not be reportable.

If you have any questions, please contact me.

Very truly yours, E,E CLUL1 nLLC m E. E. Van Brunt, Jr.

Executive Vice President Project Director EEVB/PGN/ dim Attachment cc: R. P. Zimmerman (all w/a)

A. L. Hon E. A. Licitra A. C. Gehr INPO Records Center pr 188u 8888Er 9(yp am

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s s .e PALO VERDE NUCLEAR GENERATING STATION UNIT 2 x

License No. NPF-51 Docket No. 50-529 Special Report 2-SR-86-014 This special report is submitted for informational purposes only.

On April 21, 1986, Palo Verde Unit 2 was in Mode 2 (STr TUP) at 0 percent reactor power and under the control of low power physics testing, when it was discovered that the Unit had potentially exceeded the time limits for Action i Statement #3 of Technical Specification 3.3.1. As a conservative measure, Technical Specification 3.0.3 was entered and the NRC Operations Center was notified of this action at 0655 on April 21, 1986.

Technical Specification 3.3.1, Table 3.3-1 requires three Core Protection Calculator (CPC) System Channels OPERABLE for Mode 2. One channel was already in bypass when a second channel was declared INOPERABLE. When two channels are INOPERABLE, Action #3 requires one channel be verified in bypass and one channel placed in the trip position within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. This action was not completed; however, further evaluation revealed that Action Statement #3 is not applicable during Startup Physics Testing pursuant to notation "D" of Table 3.3-1. Technical Specification 3.0.3 was exited 15 minutes after entry and the event was terminated.

I Notation 'D' of Table 3.3-1 states that the limitations and requirements of Table 3.3-1 may be suspended during the performance of Startup Physics Tests i provided that:

a. The THERMAL POWER does not exceed 5% of RATED THERMAL POWER, and

b. The reactor trip setpoints of the OPERABLE power level channels are set at less than or equal to 20% of RATED THERMAL POWER.

c. Both reactor coolant loops and at least one reactor coolant pump in each loop are in operation.

Since these requirements were met, this event has been determined to be not reportable and this special report is submitted for information only.

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