ML18012A841
| ML18012A841 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 07/18/1997 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18012A840 | List: |
| References | |
| 50-400-97-06, 50-400-97-6, NUDOCS 9707310112 | |
| Download: ML18012A841 (2) | |
Text
NOTICE OF VIOLATION Carolina Power 5 Light Company Shearon Harris Unit 1 Docket No. 50-400 License No. NPF-63 During an NRC inspection conducted from Hay 11 through June 21,
- 1997, violations of.NRC requirements were identified.
In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions,"
NUREG-1600, the violations are listed below:
A.
Technical Specification 3.3. 1 requires, as a minimum, that the Reactor Trip System instrumentation channels and inter locks of Table 3.3-1 shall be operable.
Technical Specification Table 3.3-1 specifies a minimum of three Power Range Nuclear Instrumentation channels (out of four total) are required to be operable for the Neutron Flux High Positive Rate trip
- function, and that Action Statement 2 applies.
Table 3.3-1 Action Statement 2 states, in part, that Power Operation may proceed with the number of operable channels one less than the total number of channels provided the inoperable channel is placed in the tripped condition within six hours and the minimum channels operable requirement is met.
Table 3.3-1 Action 2b contains provisions for bypassing the inoperable channel for up to four hours for surveillance testing of the other channels per Specification 4.3.1.1.
Contrary to the above, on June 8, 1997. while performing surveillance testing per Specification 4.3.1.1, licensee personnel failed to restore inoperable Power Range nuclear instrumentation channel (N41) to oper able status or bypass it prior to performing surveillance activities on one of the other three channels (N42, N43 or N44).
The surveillance activity involved a course gain adjustment which input a false high positive rate trip on channel N42 coincident with N41 already being in an inoperable and tripped condition.
This satisfied two-out-of-four logic and resulted in an automatic reactor trip from 28 percent power.
This is a Severity Level IV violation (Supplement I).
B.
Technical Specification 6.5.1.1.1 requires a safety and a technical evaluation to be prepared for each procedure required by Technical Specification 6.8
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This includes surveillance procedures for reactor protection system tests and calibrations Lincor porated by reference in Regulatory Guide 1.33, Appendix A, item B.b.(1)(l)j.
Technical Specification 6.5.1.2.1 states that technical evaluations will be performed by personnel qualified in the subject matter and will determine the technical adequacy and accuracy of the proposed activity.
Contrary to the above, prior to Hay 14, 1997, the licensee failed to perform an adequate technical evaluation of maintenance surveillance test procedure NST-I0072, Revision 7, in that a deficiency was not identified, resulting in a single-train safety injection event.
The safety injection resulted, in approximately 126 gallons of refueling Enclosure 1
97073iOi i2 970718 PDR ADQCK OMOOCQO 8
CPLL water storage tank water being gravity fed into the reactor coolant system.
This is a Severity Level IV violation (Supplement I).
.C
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10 CFR 50, Appendix B, Criterion XVI requires that measures be established to assure that conditions adverse to quality such as deficiencies, deviations;.
and nonconformances are promptly identified and corrected.
These requirements are further delineated in Section 12 of the licensee's corporate Quality Assurance Program Hanual, Revision 18.
Contrary to the above, as of June 2, 1997, the licensee failed to take adequate corrective actions to resolve binding problems for the motor-driven auxiliary feedwater pump flow control valves following post-maintenance test failures.
This is a Severity Level IV violation (Supplement I).
Pursuant to the provisions of 10 CFR 2.201, Carolina Power and Light Company 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 Regional Administrator, Region II, and a copy to the NRC Resident Inspector at the facility that is the subject of this Notice, within 30 days of the date of the letter transmitting this Notice of Violation (Notice).
This reply should be clearly marked "Reply to a Notice of Violation" and should include for each violation:
(1) the reason for the violation, or, if contested, the basis for disputing the violation, (2) the corrective steps that have been taken and the 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 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 time.
Because your response will be placed in the NRC Public Document Room (PDR), to the extent possible, it should not include any personal privacy, Droprietary, or safeguards information so that it can be placed in the PDR without redaction.
However, if you find it necessary to include such information, you should clearly indicate the specific information that you desire not to be placed in the
- PDR, and provide the legal basis to support your request for withholding the information from the public.
Dated at Atlanta, Georgia this 18th day of July 1997