ML17325A768
| ML17325A768 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 06/08/1988 |
| From: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| AEP:NRC:1060C, NUDOCS 8806160080 | |
| Download: ML17325A768 (8) | |
Text
~ ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
DOCKET 05000315 05000316
SUBJECT:
Responds to NRC 880510 ltr re violations noted in Insp Repts 50-315/88-12
& 50-316/88-14.
DISTRIBUTION,CODE: IE0ID COPIES RECEIVED: LTR ENCL
/
SIZE:
TITLE: General (50 Dkt)-Insp Rept/Notice of Vio ation Response NOTES CCESSION NBR:8806160080 DOC.DATE: 88/06/08 NOTARIZED: NO CIL:50-315 Donald C.
Cook Nuclear Power Plant, Unit 1, Xndiana 50-316 Donald C.
Cook Nuclear Power Plant, Unit 2, Indiana AUTH.NAME AUTHOR AFFILIATION ALEXICH,M.P.
(formerly Indiana
& Michigan Ele RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
D RECIPIENT XD CODE/NAME PD3-1 PD INTERNAL AEOD NRR MORISSEAU,D NRR/DLPQ/QAB 10 NRR/DREP/EPB 10 NRR/DRIS DIR 9A NUDOCS-ABSTRACT OGC 15-B-18 RES/DRPS DEPY ERNAL: LPDR NSIC COPIES LTTR ENCL 1
1 1
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1 RECIPIENT ID CODE/NAME STANG,J DEDRO NRR/DLPQ/PEB 11 NRR/DOEA DIR 11 NRR/DREP/RPB 10 NRR/PMAS/ILRB12 OE LXEBERMAN,J G
02 RGN3 FILE 01 NRC PDR COPXES LTTR ENCL 2
2 1
1 1
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2 1
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TOTAL NUMBER OF COPIES REQUIRED:
LTTR 23 ENCL
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Indiana Michigan Power Company P0 Sox I663I Co',urnous, 08 ~32 I6 INDIANA NICHIGAN POWER AEP: NRC: 1060C Donald C.
Cook Nuclear Plant Units 1 and 2
Docket Nos.
50-315 and 50-316 License Nos.
DPR-58 and DPR-74 NRC INSPECTION REPORT NOS.
50-315/88012 (DRP)
AND 50-316/88014 (DRP);
RESPONSE
TO VIOLATION U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.
20555 Attn:
A. B. Davis June 8, 1988
Dear Mr. Davis:
This letter is in response to W.
G. Guldemond's letter dated May 10, 1988, which forwarded the report on the routine safety inspection conducted by members of your staff.
This inspection was conducted from March 15 through April 25,
- 1988, on activities at the Donald C.
Cook Nuclear Plant Units 1 and 2.
The Notice of Violation attached to Mr. Guldemond's letter identified one violation.
This violation is addressed in the attachment to this letter.
This document has been prepared following corporate procedures which incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned.
Very truly yours, M.
. Ale ich Vice President MPA/ldp cc:
D. H. Williams, Jr.
W.
G. Smith, Jr.
- Bridgman R.
C. Callen B. Bruchmann G. Charnoff NRC Resident Inspector
- Bridgman A. B. Davis egp616ppeK p5ppp315-p gsp6ps
@OR pOO~K ore 0
ATTACHMENT TO AEP:NRC:1060C
RESPONSE
TO VIOLATION
NRC VIOLATION "Technical Specification Surveillance Requirement 4.3 '.1.1 requires that each reactor trip system instrumentation channel shall be demonstrated
[operable]
by the performance of a CHANNEL CHECK for the MODES and at the frequencies shown in Table 4.3-1.
"Table 4.3-1 "Reactor Trip System Instrumentation Surveillance Requirements" requires that a CHANNEL CHECK of the power range neutron flux instruments
[be performed] at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when in MODES 1 or 2 and when the reactor trip system breakers are closed and the control rod drive system is capable of rod withdrawal.
"Contrary to the above, during June 26 through June 29,
- 1986, and again during April 16,
- 1987, through April 20,
- 1987, the licensee failed to perform the CHANNEL CHECKS at the required 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> frequency while Unit 2 was in MODE 3 with the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal.
The longest interval where a CHANNEL CHECK was not performed as required was 35 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br />."
RESPONSE
TO NRC VIOLATION (1)
CORRECTIVE ACTION TAKEN AND RESULTS ACHIEVED On February 5,
1988, during procedure revision work for the Operations Department daily and shift surveillance procedure 1(2)-OHP 4030.STP.030, it was identified that channel checks of the power range nuclear instrumentation were only required in Modes 1 and 2.
Change sheets were written to the involved Unit 1 and Unit 2
,procedures on February 5,
1988, to require channel checks of the power range nulcear instrumentation whenever the control rod drive system is capable of control rod withdrawal.
These changes made the involved procedures consistent with the amended Technical Specifications.
The procedural deficiency was caused by cognitive personnel error when reviewing the Technical Specification amendment for impact
'on plant procedures, which added the requirement to perform the channel checks whenever the control rod drive system is capable of control rod withdrawal.
A second review of the Technical Specification amendment for impact on Operations Department procedures was completed on March 3, 1988.
No additional deficiencies were identified.
(2)
CORRECTIVE ACTION TO BE TAKEN TO AVOID FURTHER VIOLATION The instructions addressing the review and implementation of Technical Specification amendments are contained in PMI-4030 "Technical Specification Review and Surveillance".
Currently PMI-4030 only requires one technical review by each plant department for impact on procedures.
PMI-4030 will be revised to require a second technical review by each department for future Technical Specification amendments.
(3)
DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED Full compliance was achieved on February 5, 1988, when procedures 1(2)-OHP 4030.STP.030 were revised via change sheet.
PMI-4030 will be revised by June 24, 1988.