ML17300B037

Special Rept 2-SR-87-022:on 870828,unusual Event Declared Due to Release in Excess of 6.62 E-4 Mci Per Cubic Centimeter.Cause Under Investigation.Corrective Action Will Be Developed Based on Investigation Results

ML17300B037
Person / Time
Site:	Palo Verde
Issue date:	09/01/1987
From:	Haynes J ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
192-00274-JGH-T, 192-274-JGH-T, 2-SR-87-022, 2-SR-87-22, NUDOCS 8709100331
Download: ML17300B037 (4)

Text

REGULAT Y INFORMATION DISTRIBUTIO "YSTEM (RIDS) el ACCESSION NBR: 8709100331 DOC. DATE: 87/09/01 NOTARIZED: NO DOCKET FACIL: STN-50-529 Palo Verde Nuclear Station> Unit 2> Ari zona Pub li 05000529 AUTH. NAME AUTHOR AFFILIATION HAYNESI J. G. Arizona Nuclear Power Prospect (formerly Arizona Public Serv RECIP. NAME RECIPIENT AFFILIATION Document Control Branch'Document Control Desk)

SUBJECT:

Special'ept 2-SR-87-022: on 870828I notification of unusual event declared due to release in excess of 6. 62 E-4 mCi per cubic centimeter. Caused under investigation. Corrective action will be developed based on investigation results.

DISTRIBUTION CODE: IE22D COPIES RECEIVED: LTR Q ENCL TITLE: 50. 73 Licensee Event Report (LER) I Incident Rpti etc.

g SIZE: 3 NOTES: Standardized plant. 05000529 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 LA 1 1 PD5 PD 1 -

1 L IC l'TRAI E 1 1 DAVISI M 1 1 INTERNAL: ACRS MICHELSQN 1 ACRS MOELLER 2 2 AEOD/DOA 1 1 AEOD/DSP/NAS 1 1 AEOD/DSP/RQAB 2 2 AEOD/DSP/TP*B 1 1 DEDRQ 1 1 NRR/DEST/ADS 0 NRR/DEST/CEB 1 1 NRR/DEST/ELB 1 1 NRR/DEST/ICSB 1 NRR/DEST/MEB 1 1 NRR/DEST/MTB 1 1 NRR/DEST/PSB 1 1 NRR/DEST/RSB 1 "1 NRR/DEST/SGB 1 1 NRR/DLPG/HFB 1 1 NRR/DLPG/GAB 1 NRR/DOEA/E*B 1 1 NRR/DREP/RAB 1 1 P/RPB 2 2 NRR /PMAS/ ILRB 1 1 R FIL 02 1 1 RES DEPY GI 1 1 ORDI J 1 1 RES/DE/EIB 1 1 RGN5 F ILE'1 1 1 EXTERNAL: EG&G GROHi LPDR M 5 1

5 H ST LOBBY WARD NRC PDR 1:

1 1

NS I C H*RR ISI J 1 1 NSIC MAYSI G NOTES:

TOTAL NUMBER OF COPIES REQUIRED: LTTR 45 ENCL 44

4 lt ~

Arizona Nuclear Power Project P.O. SOX 52034 ~ PHOENIX. ARIZONA 85072-2034 192-00274-JGH-TRB/MJC September 1, 1987 U.S. Nuclear Regulatory Commission NRC Document Control Desk Washington, D.C. 20555

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

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

Special Report 2-SR-87-022 File: 87-020-404

Dear Sirs:

Attached please find a Special Report 2-SR-87-022 prepared and submitted pursuant to Emergency Plan Implementing Procedure -02. This report discusses a NOTIFICATION OF UNUSUAL EVENT due to a gaseous effluent release.

If you have any questions, please contact T. R. Bradish, Compliance Supervisor at (602) 393-3531.

Very tru y yours, VA ~r~-

J. G. Haynes Vice President Nuclear Production JGH/TRB/MJC/cld Attachment cc: 0. M. DeMichele (all w/a)

E. E. Van Brunt, Jr.

J. B. Martin J. R. Ball E. A. Licitra A. C. Gehr INPO Records Center rgb' 87091OO331 87O9Oi PDR ADQCK OSODOM9 S PDR

PALO VERDE NUCLEAR GENERATING STATION NOTIFICATION OF UNUSUAL EVENT Docket No. 50-529 License No. NPF-51 Special Report No. 2-SR-87-022 At approximately 1715 MST on August 28, 1987, the USNRC Operations Center was notified via the Emergency Notification System of the declaration of a NOTIFICATION OF UNUSUAL EVENT (NUE) for Palo Verde Nuclear Generating Station Unit 2. The NUE was declared pursuant to Emergency Plan Implementing Procedure EPIP-02 which requires the submission of a report for a plant vent release in excess of 6.62 E-4 Micro Curies (Ci) /cubic centimeter (cc).

Prior to the event, with Unit 2 in Mode 1 (POWER OPERATION) at 100 percent power, preparations were being made to perform corrective maintenance on the "B" waste gas decay tank (WGDT) relief valve. Preparations included draining and venting of the gaseous radw'aste surge tank and WGDT "B". During the venting process, an alarm was received on the low range plant vent radiation monitor (RU-143). Radiation levels had increased to approximately 7.79 E-4 micro Ci/cc.

This is in excess of the NUE setpoint (6.62 E-4 micro Ci/cc) specified in EPIP-02.

Radiation Protection technicians verified that the alarm received on RU-143 was valid and at approximately 1715 MST, the shift supervisor declared an NUE and the appropriate notifications were made. The NUE was terminated concurrent with the declaration since the plant vent release concentrations had decreased below 6.62 E-4 micro Ci/cc by 1715 MST.

Evaluation of the event determined that the exposure limits specified in Technical Specifications were not exceeded and the event did not hamper site personnel in their duties necessary for the safe operation of the plant. An investigation of the cause of the event is currently in process. Corrective action necessary to prevent recurrence will be developed based on the results of the investigation.