IR 05000620/2008017
| ML17332A920 | |
| Person / Time | |
|---|---|
| Site: | Cook, 05000620  |
| Issue date: | 09/12/1995 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML17332A919 | List: |
| References | |
| 50-315-95-09, 50-315-95-9, 50-316-95-09, 50-316-95-9, NUDOCS 9509190061 | |
| Download: ML17332A920 (6) | |
Text
NOTICE OF VIOLATION Indiana Michigan Power Company Donald C.
Cook Nuclear Power Plant Docket No. 50-315; 5-316 License No.
DRP-58; DPR-"74 During an NRC inspection conducted June 20 through August 17, 1995, violations of NRC requirements were identified.
In accordance with the "General Statement of Policy and Procedures for NRC Enforcement"Actions,"'60 FR 34381';
June 30, 1995) the violations are listed below:
D. C.
Cook Plant Technical Specification 6.8.1 states, in part, that written procedures shall be established, implemented, and maintained covering the applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978.
The following are examples of failure to follow procedures:
Regulatory Guide 1.33, Appendix A, paragraph 6.e requires that a
loss of condenser vacuum procedure be written as part of procedures available for combating emergencies and other significant events.
Operations Department Procedure
~*01-OHP 4024. 118, Revision 6,
"Annunciator ¹118 Response:
Main and FPT," step 3. 1 of "Drop 71" states:
"Reduce turbine load as rapidly as possible."
Contrary to the above, on July 14, 1995, the operators failed to reduce power during a loss of main turbine condenser vacuum transient.
Regulatory Guide 1.33, Appendix A, paragraph 2.e. requires that plant operations procedures be written for turbine startup and synchronization of the generator.
Operations Department Procedure
- 01-OHP 4021.050.001, Revision 11, "Turbine Generator Normal Startup and Operation,"
step 4.3. 15 states:
"Place I-GCH-11, Generator Core Monitor, in service per Attachment l."
C.
Contrary to the above, on July 16, 1995, the operators failed to place the Generator Core Monitor in service.
Regulatory Guide 1.33, Appendix A, paragraph 9.d requires that procedures categorized as maintenance or operating procedures be written'or exercising of equipment that is normally idle but must operate when required.
Procedure 12 EHP.6040. PER. 141, step 5. 17 states that if a main steam safety valve (HSSV) cannot be exercised, stop testing immediately and notify the shift supervisor (SS).
9509i900bi 9509i2 PDR ADGCK 050003i5
Contrary to the above, on June 19, 1995, with the unit at approximately 55 percent power, the licensee began exercising the Unit 1 MSSVs.
While testing MSSV 1-SV-3-2, which had a setpoint of 1085 psig, the equivalent of 1180 psig was applied without the valve lifting.
The SS and control room operators were not informed that testing had stopped because 1-SV-3-2 would not lift.
This is a Severity Level IV Violation (Supplement I). (315/316/95009-01)
CFR Part 50.72, paragraph (b)(1)(ii)(B) requires that a condition outside the design basis of the plant be reported to the NRC within one.
hour of occurrence.
CFR Part 50.72, paragraph (b)(2)(ii) requires that any event or condition that results in a manual or automatic actuation of any engineered safety feature be reported to the NRC within four hours of occurrence.
Contrary to the above, a.
On July 4, 1995, the licensee failed to report the temporary loss of automatic four loop ECCS injection capability.
This condition is outside the accident analysis currently docketed and approved by the NRC.
On October 12, 1994, the licensee failed to report a phase
"A" containment isolation signal that resulted in the unexpected isolation of the Unit 2 containment purge valves'he phase
"A" containment isolation signal is listed as part of the ESF actuation system instrumentation in paragraph 9.a of Table 3.3-3 of TS.
C.
On July, 28, 1995, the licensee failed to report the unexpected automatic start of the Unit
TDAFW pump during a power source transfer evolution.
The autostart signal for the TDAFW pump due to reactor coolant pump bus undervoltage is listed as part of the ESF actuation system instrumentation in paragraph 7.b of Table 3.3-3 of TS.
d.
On April 2, 1994, the licensee failed to report the inoperabilty of both trains of Unit 2 engineered safety feature exhaust fans, a
condition outside the design basis of the plant.
This is a Severity Level IV violation.
(Supplement I)(315/316/95009-02)
I
CFR Part 50, Appendix B, Criterion XI, "Tes't 'C'ontrol," requires that a test program be established to assure that all testing required to demonstrate that structures, systems, and components will perform satisfactorily in service is identified and performed.
Contrary to the above, the l"icensee d'id not perform adequate testing following maintenance to assure that the following components would perform their intended function satisfactorily:
a.
b.
The Unit 1 main generator voltage regulator was not tested following potentiometer replacement.
This resulted in oyer-excitation of the main generator and damage to the main transformer during a subsequent generator paralleling evolution.
A slow start was performed on the Unit 2 "AB" EOG following replacement of the turbocharger starting air assist insert.
Starting air is not supplied to the turbocharger during a slow start.
C.
Following the post-maintenance testing on the "West" Diesel-driven fire water pump following work on pressure regulating valve 12-ZRV-404, the system was declared operable despite being unable to maintain designed system pressure.
This is a Severity Level IV violation (Supplement I).(315/316/95009-03)
Pursuant to the provisions of 10 CFR 2.201, Donald C.
Cook is hereby required to submit a written statement or explanation to the U.S. Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, D.C.
20555 with a copy to the U.S. Nuclear Regulatory Commission, Region I!I, 801 Warrenville Road, Lisle, Illinois.60532 and a copy to the NRC Resident Inspector at the Donald C.
Cook Nuclear Power Plant within 30 days of the date of the letter transmitting this Notice of Violation (Notice).
This reply should be clearly marked as a "Reply to the Notice of Violation" and should include:
(1) the reason for the violations, or, if contested, the basis for disputing the violations, (2) the corrective steps that have been taken and results achieved, (3) the corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will be achieved.
Your response may reference or include previous docketed correspondence, if the correspondence adequately addresses the required response.
If an adequate reply is not received within the time specified in this Notice, an order or a
Demand 'for information may be issued as to why the license should not be modified, suspended, or revoked, or why such other action as may be proper should not be taken.
Where good cause is shown, consideration will be given to extending the response tim Notice of Violation Because the response will be placed in the NRC Public Document Room (PDR), to the extent possible, it should not include any personal privacy, proprietary, or safeguards information so that it can be placed in the PDR without reductions However, if it is necessary to include such information, it should clearly indicate the specific information that should not be placed in the PDR, and provide the legal basis to support the request for withholding the information from the public.
Dated at Lisle, Illinois this 12th day of September, 1995