ML20079H238
| ML20079H238 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 01/10/1984 |
| From: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| Shared Package | |
| ML20079H222 | List: |
| References | |
| AEP:NRC:0859, AEP:NRC:859, NUDOCS 8401230374 | |
| Download: ML20079H238 (3) | |
Text
.
INDIANA & MICHIGAN El.ECTRIC COMPANY P.O. BOX 16631 COLUMBUS, OHIO 43216 January 10, 1984 AEP:NRC:0859 Donald C. Cod L clear Plant Unit Nos. 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 NRC Inspection Report 83-16/83-17 (DPRP)
Mr. James G. Keppler U. S. Nuclear Regulatory Commission Region III 799 Ecosevelt Road Glen Ellyn, Illinois 60137
Dear Mr. Keppler:
This letter is in response to Mr. W. D. Shafer's letter dated November 23, 1983, which forwarded the subject Inspection Report of the routine safety inspection conducted by your staff at the Donald C. Cook Nuclear Plant during the period September 10 through October 20, 1983.
The Notice of Violation attached to Mr. Shafer's letter identified two (2) items of noncompliance. Per Mr. P. A. Barrett's conversation with Mr. M. Holzmer on December 22, 1983, an extension to January 10, 1984 was granted to us to complete our responses to these items. Our responses to these items are presented below.
_ Item 1 (Unit 1)
" Unit 1 Technical Specification 3.9.7 states:
' Loads in excess of 2500 pounds shall be prohibited from travel over fuel assemblies in the storage pool. Loads carried over the spent fuel pcol and heights at which they may be carried over racks containing fuel shall be limited in such a way as to preclude impact energies over 24,240 in.-lbs., if the loads are dropped from the crane.*'
Procedure 12 MHr5021.001.036 implements Specification 3.9.7 and requires that ha vy loads be transported only over color coded safe load zones.
Contrary to the above, on September 29, 1983 a 55 ton shield block was transported outside the designated safe loa 6 zone."
RESPONSE TO ITEM 1 1.
CORRECTIVE ACTION TAKEN AND RESULTS ACHIEVED One of the concrete shield blocks was moved above an area not included within the safe load path boundaries, in violation of the procedure. The individuals supervising the activity were aware of the procedural requirements. Beca m of minor difficulties 8401230374 840118 hDRADOCK 05000315 3 @A eDe p1
Mr. Jame3.G. Kcpp10r AEP:NRC:0859 l
(-
. encountered, the shield block was transported above an area adjacent to the Spant Fuel Pit which was not includ9d within the safe load path boondaries in order to expedite job completion.
I The.NRC Senior Resident Inspector observed the activity and informed appropriate Plant Management. The responsible individuals were directed to complete the movement of the remaining shield blocks in accordance with the procedure requirements. All subsequent movements of shield blocks were conducted within the safe load path boundaries.
2.
CORRECTIVE ACTION TAKEN TO AVOID TURTHER NONCOMPLIANCE The Civil Constraction Department Head reinstructed the rosponsible individuals in the proper use of established procedures.
Compliance with all procedural requirements was stressed. A contributing factor to this occurrence was that the current hook was not easily swivelled. A design change (RFC-DC-1953) has been initiated to correct this situation.
3.
DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED Full compliance hs been achieved.. Compliance with the established procedures is not dependent upon RFC-DC-1953.
ITEM 2 (Unit 2)
" Unit 2' Technical Specification 6.8.1.c states:
' Written procedures shall be established, implamented and maintained covering the
... surveillance and test activities of safety related equipment....'
To comply with Technical Specification Surveillance 4.5.4.1, procedure 12 THP 6020. LAB.037 ' Techniques of Liquid Sampling' specifies that to sample the Boron Injection Tank (BIT) for boron concentration, sample valve SI-131 be opened and then closed after flushing and drouing the
- sample, a.
Contrary to the above on September 26, 1983, the sample valve was not closed following sampling of the BIT thereby degrading the operability of the system.
~
b.
Contrary to the above, the sampling of the BIT requires operation of two valves, SI-131 and SI-209, and procedure 12 THP6020 LAB.037 does not address operation of the valve SI-209."
RESPONSE TO ITEM 2.a.
1.
CORRECTIVE ACTION TAKEN AND RESULTS ACHIEVED The technician who left the BIT sample valve open was removed from the technician shift rotation and given duties that did not require
. sampling any safety related systems. This technician was also placed into a requalification program for retraining in her job classification.
________________________m
Mr. James G. Kcpplcr AEP:NRC:0859 e
2.
CORRECTIVE ACTION TAKEN TO AVOID FURTHER NONCOMPLIANCE This sample point in particular and all sample points on safety related equipment (or equipment vital to the plant or plant safety) are now monitored by a program of double valve verification by two individuals.
3.
DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED _
Full compliance has been achieved.
RESPONSE TO ITEM 2.b.
1.
CORRECTIVE ACTION TAKEN AND RESULTS ACHIEVED The procedure covering sampling of the boron injection tank was l
changed to reflect the extra valve present on Unit 2.
l l
l-2.
CORRECTIVE ACTION TAKEri TO AVOID FURTHER NONCOMPLIANCE t
A senior technician evaluated all our sampling procedures to insure the physical work being done and the written procedure steps were identical.
3.
DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED Full compliance has been achieved.
This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to insure its accuracy and completeness prior to signature by the undersigned.
Very truly yours,
(
Ik P.
..lexich Vice esident MPA/pb cc: John E. Dolan W. G. Smith, Jr. - Bridgman R. C. Callen G. Charnoff E. R. Swanson, NRC Resident Inspector - Bridgman f
- _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _. _ _ _ _ _ _ _ _ _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _..