ML17333A540
| ML17333A540 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 08/16/1996 |
| From: | Blind A AMERICAN ELECTRIC POWER CO., INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9608200230 | |
| Download: ML17333A540 (5) | |
Text
ACCESSION i98R:9608200230 DOC.DATE: 96/08/16 NOTARIZED:
NO DOCKET FACIL:50-315 Donald C.
Cook Nuclear Power Plant, Unit 1, Indiana M
05000315 AUTH.NAME AUTHOR AFFILIAT ON BLIND,A.A.
American Electric Power Co., Inc.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Special rept:on 960814,determined radiation monitor inoperable since isolation of 1-MRV-213 on 960802.1-MRV-213 leakby problem will be corrected, when parts become available, tentatively scheduled for Oct.
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TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.
NOTES:
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RECIPIENT ID CODE/NAME PD3-1 PD INTERNAL: AEOD/SPIgHhB ER DP/-EEL'RR/DRCH/HHFB NRR/DRCH/HOLB NRR/DRPM/PECB NRR/DSSA/SRXB RGN3 FILE Ol EXTERNAL: L ST LOBBY WARD NOAC MURPHY,G.A NRC PDR COPIES LTTR ENCL RECIPIENT ID CODE/NAME HICKMANgJ AEOD/SPD/RRAB NRR/DE/ECGB NRR/DE/EMEB NRR/DRCH/HICB NRR/DRCH/HQMB NRR/DSSA/SPLB RES/DSIR/EIB LITCO BRYCEgJ H
NOAC POORE,W.
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0
American Electric Po Cook Nuclear Plant One Cook Place Sridgman, Ml 49106 616 465 5901 AhlERICAN ELECfRIC POMfER Donald C. Cook Nuclear Plant Unit 1 Docket No. 50-315 License No. DPR-58 Special Report, Technical Specification 3.3.3.1 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 August 16, 1996 Gentlemen:
This Special Report is being submitted in accordance with Technical Specification (TS) 3.3.3.1, Action Statement 22B, to inform the NRC that the Steam Generator (SG) Power Operated Relief Valve (PORV)
Radiation Monitor for Loop 1, 1-MRA-1601, was inoperable longer than allowed by the Action Statement.
On August 2, 1996, at 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br />, the PORV for Steam Generator ¹1, 1-MRV-213, was isolated. The valve had been observed to be leaking by as evidenced by wisps of steam exhausting to atmosphere.
The manual isolation valve upstream of 1-MRV-213 was closed, effectively isolating the leakage.
During preparation ofthe draft Safety Evaluation for extended operation of the unit with this valve configuration, itwas determined that operation with 1-MRV-213 isolated affected operability of the downstream radiation monitor.
1-MRA-1601 monitors the gaseous eNuent flowfrom a location on the SG
¹1 PORV discharge vent to atmosphere.
The physical location of the monitor required an exemption from the requirements of NUREG-0737, Item II.F.1, due to the possibility of steam flow bypassing the monitor should the safety valve(s) liftduring a Steam Generator Tube Rupture (SGTR). An exemption was granted by the NRC on April 6, 1990, after a review of the plant configuration and the alternate monitoring methods in place.
On August 14, 1996, itwas determined that the radiation monitor had been inoperable since the isolation of 1-MRV-213 on August 2, 1996, and that the 7 day Action Statement for return to operability had not been met. Because the monitor was not returned to service prior to August 9, 1996, a Special Report must be submitted within 14 days of the event, in accordance with Action Statement 22B of TS 3.3.3.1. This letter shall serve to fulfillthe requirements of the Special Report.
While 1-MRA-1601 was inoperable, permanent procedures were in place that served as compensatory actions. These procedures, which were reviewed and approved by the NRC prior to the granting of the exemption issued for the physical location of 1-MRA-1601, consist of an Emergency Plan procedure that contains diverse methods for determining release levels from the Main Steam System in the event that the PORV vent path is unavailable.
The procedure, PMP 2081.EPP.107 "Alternate Release Level Determinations", would be used ifthe radiation data display system is inoperable or ifa radiation monitor is offscale or bypassed.
Four major effluent paths are considered in the procedure: the gland seal leak off, the SJAE exhaust, the unit vent, and Main Steam (SG safeties/PORV).
The method of estimating a release rate involves sending out radiation monitoring teams to predesignated locations to obtain dose rate measurements or grab samples.
Release rate is then determined by multiplying the dose rate or grab sample results by the appropriate correct factors.
9608200230 9608ih PDR ADQCK 050003i5 S
Special Report August 16, 1996 Page 2 of2 PMP 2081.EPP.107 also includes a method to estimate release rate ifsampling and monitoring data is unavailable or cannot be obtained in time to support a dose assessment.
This method involved the use of a logic diagram that utilizes information on plant conditions, when it is available, and utilizes conservative default values when information on plant conditions is unavailable.
The block valve upstream of 1-MRV-213 was reopened on August 14, 1996 at 1605 hours0.0186 days <br />0.446 hours <br />0.00265 weeks <br />6.107025e-4 months <br />, and 1-MRA-1601 returned to service and declared operable. The 1-MRV-213 leakby problem willbe corrected when parts become available, tentatively scheduled for October.
A. A. Blind Site Vice President c:
A. B. Beach, Region III E. E. Fitzpatrick NRC Resident Inspector NFEM Section Chief, State of Michigan