ML17305B755
| ML17305B755 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 09/22/1991 |
| From: | Conway W ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| Shared Package | |
| ML17305B756 | List: |
| References | |
| 161-04172-WFC-M, 161-4172-WFC-M, NUDOCS 9110010192 | |
| Download: ML17305B755 (5) | |
Text
A('('BERATED DI TRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9110010192 DOC.DATE-91/09/22 NOTARIZED: NO DOCKET FACIL:STN-50-528 Palo Verde Nuclear Station, Unit 1, Arizona Publi 05000528 AUTH.NAME AUTHOR AFFILIATION CONWAY,W.F.
Arizona Public Service Co.
(formerly Arizona Nuclear Power RECIP.NAME RECIPIENT AFFILIATION MARTIN,J.B.
Region 5 (Post 820201)
SUBJECT:
Forwards Rev 0 to JCO-91-01-00, "Justification for Continued Operation Palo Verde Unit 1,Potential for Small Break LOCA due to Pipe Rupture in Reactor Coolant Pump Seal Cooler."
DISTRIBUTION CODE: IEOID COPIES RECEIVED: LTR ENCL 0 SIZE:
TITLE: General (50 Dkt)-Insp Rept/Notice of Vi&o ation Response D
NOTES: STANDARDIZED PLANT 05000528 RECIPIENT ID CODE/NAME PD5 PD THOMPSON,M INTERNAL: ACRS AEOD/DEIIB DEDRO NRR MORISSEAU,D NRR/DLPQ/LPEB10 NRR/DREP/PEPB9H NRR/PMAS/ILRB12 OE DX~
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1 RECIPIENT ID CODE/NAME TRAMMELL,C AEOD AEOD/DSP/TPAB NRR HARBUCK,C.
NRR SHANKMAN,S NRR/DOEA/OEAB NRR/DST/DIR 8E2 NUDOCS-ABSTRACT OGC/HDS1 RGN5 FILE 01 NRC PDR COPIES LTTR ENCL 1
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NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT. 20079) TO ELliVIINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 26 ENCL 26 D
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Arizona Public Service Company P.O, BOX 53999
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PHOENIX. ARIZONA85072.3999
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WILLIAMF. CONWAY EXECUTIVEVICEPRESIDENT NUCLEAR Docket No.
STN 50-528 161-04172-WFC/MEP/KLMC September 22, 1991 Mr. John B. Martin Regional Administrator, Region V
U.S. Nuclear Regulatory Commission 1450 Maria Lane, Suite 210 Walnut Creek, California 94596
Reference:
Letter to USNRC from W.
F.
- Conway, APS, dated April 13, 1991.
Subject:
Justification for Continued Operation
- Potential for Small Break Loss of Coolant Accident due to Pipe Rupture in the Reactor Coolant Pump Seal Cooler, Revision 1 (161-03873).
Dear Mr. Martin:
Subj ect:
Palo Verde Nuclear Generating Station (PVNGS)
Unit 1
Justification for Continued Operation
- Potential for Small Break Loss of Coolant Accident Due to Pipe Rupture in the Reactor Coolant Pump Seal Cooler, Revision 0.
File 91-056-026 The referenced letter provided a Justification for Continued Operation (JCO) for PVNGS Units 1, 2,
and 3, until the implementation of a design modification on each unit, which would mitigate the consequences of a Small Break Loss of Coolant Accident (SBLOCA) due to a
pipe rupture in a
reactor coolant pump seal cooler.
The compensatory measures in the JCO specified an administrative limit for equilibrium dose equivalent iodine of 0.2 uCi/gm.
Since submittal of the JCO, the PVNGS Unit 1 equilibrium I-131 dose equivalent increased to approximately 0.16 uCi/gm, prior to the reactor trip on September 14, 1991.
Post trip RCS sampling indicated an iodine concentration of 2.35 uCi/gm.
Although this concentration was with'n Technical Specification 3.4.7 requirements, a reevaluation of the JCO was performed to justify an increase to the administrative limit for equilibrium dose equivalent iodine to 0.4 uCi/gm.
This increase will allow operation above the current administrative limit of 0.2 uCi/gm until the Unit 1 refueling outage in February 1992.
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161-04172-WFC/MEP/KLMC September 22, 1991 Mr. J.
B. Martin U.S. Nuclear Regulatory Commission Justification for Continued Operation
- Unit 1 SBLOCA Page 2
Arizona Public Service Company (APS) is herewith submitting a
PVNGS Unit 1 JCO to increase the administrative limit for equilibrium DOSE EQUIVALENT iodine to 0.4 uCi/gm.
APS considers the increased limit to be justifiable for the following reasons:
o The JCO will be in effect for Unit 1 only until the upcoming refueling outage in February 1992.
o The probability of occurrence of the event is low, approximately l. 7E-5 per reactor year.
Compensatory measures are in place for the operators to detect increased activity and to take corrective action.
(Note:
On two occasions, sampling in accordance with the April 13,
- 1991, JCO was not completed as required.
The cause of these occurrences has been corrected, and sampling is being conducted as required.)
o The Exclusion Area Boundary dose remains less than 25% of 10 CFR 100 limits, should the unlikely event occur.
As indicated above, this JCO is applicable to Unit 1 only and is to remain in effect until the Unit 1 refueling outage, currently scheduled for February 1,
1992.
This JCO has been reviewed and approved by the Plant Review Board.
Please call Michael E. Powell at (602) 340-4981, if you have any questions.
Sincerely, WFC/MEP/KLMC/rw Attachment cc:
Document Control Desk D. H.
Coe C.
M. Trammell A.
C.
Gehr A. H. Gutterman
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