IR 05000400/1986017
| ML18019A784 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 04/02/1986 |
| From: | Jape F, Taylor P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18019A782 | List: |
| References | |
| 50-400-86-17, NUDOCS 8604150375 | |
| Download: ML18019A784 (8) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTASTREET, N.W.
ATLANTA,GEORGIA 30323 Report No.:
50-400/86-17 Licensee:
Carolina Power and Light Company P. 0.
Box 1551 Raleigh, NC 27602 Docket No.:
50-400 Facility Name:
Harris
Inspection Conducted:
March Inspecto
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P.
. Tay or 10-14, 1986 Cc'4~g l,
License No.:
CPPR-158 Date Soigne Approved by:
F. Jape, Sect on C ief Engineering Branch Division of Reactor Safety Dat Signed SUMMARY, V
Scope:
This routine, unannounced inspection entailed 35 inspector-hours on site in the areas of reactor coolant system cold hydrostatics test results evaluation, licensee action on previous enforcement matters, followup on inspector identified items and plant tours.
Results:
No violations or deviations were identified.
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REPORT DETAILS Persons Contacted Licensee Employees
- J. L. Wills, Plant General Manager
- E. J. Wagner, Manager, Engineering
- C. S. Hinnant, Manager, Startup
- C. L. McKenzie, Acting Director, Quality Assurance/Quality Control (QA/QC)
- M. G. Wallace, Specialist Regulatory Compliance
- R. T. 8iggerstaff, Principal Engineer, Operation Nuclear Support B. H. Clark, Startup Engineer J. Dority, Startup Supervisor, Electrical Other licensee employees contacted included engineers, operators, and office personnel.
NRC Resident Inspectors
- P.
G. Humphrey,
- G. F. Maxwell,
- Attended exit interview Exit Interview The inspection scope and findings were summarized on March 14, 1986, with those persons indicated in paragraph 1 above.
The inspector described the areas inspected and discussed in detail the inspection findings.
No dissenting comments were received from the licensee.
The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspector during this inspection.
Licensee Action on Previous Enforcement Matters (Closed)
Unresolved Item 400/85-47-02, Correct Discrepancies in Test Procedures 1-1100-P-02, Containment Isolation Test.
The inspector identified two containment isolation valves, SP-408 and SP-409 which has not been included in the test procedure and also a need to provide a verification check that the containment isolation valves did reach their isolation position.
The inspector reviewed Revision 1 to the test procedure which was issued February 28, 1986 and verified that the valves had been added to the test procedure and that other procedural discrepancies had been correcte IC
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(Closed)
Unresolved Item 400/85-47-03 Clarify Acceptance Criteria and Correct Discrepancies in Test Procedure 1-2005-P-01, Hot Functional Test.
The inspector had identified an issue with the minimum temperature requirements for completing the vibration cycles on the reactor vessel internals.
This item had not been included in the test procedure as part of the acceptance criteria.
In addition, the time requirements for establishing the passiviting film on RCS internals was not provided.
The inspector reviewed Revision 1 to the test procedure which was issued December 26, 1985 and verified that appropriate acceptance criteria had been incorporated.
(Closed)
Unresolved Item 400/86-02-05, Set Point Verification of Main Steam Safety Valves, Test Procedure 1-3020-P-06.
The set point verification of the main steam safety valves was conducted during hot functional testing.
Draft Technical Specification table 3.7-2 contains a footnote which states that the lift setting pressure shall correspond to ambient condition of the valve at nominal operating temperature and pressure.
The inspector expressed a concern on the effects it would have on the safety valve setpoint if the valve was to significantly heatup during a lift and an adjustment was made while the valve was hot.
No provision to monitor safety valve body temperature during the test had been provided.
The licensee issued procedure change No.
1 dated January 16, 1986, to require that safety valve body temperature be taken before and after lift testing each valve.
Unresolved Items Unresolved items were not identified during the inspection.
Inspector Followup Items (70301, 92701)
The following inspector followup items were reviewed with licensee management.
(Closed)
400/85-47-01 Clarify Method to Ensure Initial Condition 2.9 in Test Procedure 1-1100-P-01 will be met for all Systems and Valves.
The licensee issued Revision
(dated February 26, 1986)
to the test procedure requiring a verification sign off for each containment isolation valve being tested and the requirement that the test be conducted under normal system operating conditions.
The operating conditions shall also be described in the narrative of the test report to the test procedure.
(Closed)
400/86-02-01, Confirm System Conditions for Testing Containment Isolation valves (SI 263 and SI 264) is Satisfactor cl g I
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The inspector confirmed that the test pressure conditions provided in test procedure 1-2090-P-02, ECCS Check Valve and Containment Isolation Valve Testing, was equivalent to the operating pressure range of the cold leg accumulator.
The subject containment isolation valves are in the drain path between the accumulator and the refueling water storage tank and the pressure used does simulate the worst case flow rate condition under which the isolation valves would have to close.
(Closed)
400/86-02-03 and 400/86-02-04, Confirm Method for Timing Pressurizer PORV Block Valves and Main Steam Isolation Valves.
The licensee issued procedure change No.
1 to test procedure 1-2005-P-04 (dated, January 12, 1986) requiring that the PORV block valves be timed from the point of turning the hand switch in lieu of observing a change in light status for starting the time.
The method prescribed for timing MSIV closure is from initiation of the steam line isolation signal which is acceptable.
6.
Reactor Coolant System (RCS) Hydrostatic Test Results Evaluation (70562)
The inspector reviewed the test results of test procedure 1-2005-C-01, RCS Cold Hydrostatic Test, Revision 1, approved September 25, 1984, to verify that Test steps and data sheets identified data recorder Test results met the acceptance criteria Changes made to the procedure did not change the purpose of the test The licensee had evaluated the test results and management approval received as required by administrative controls Deficiencies identified during the test were evaluated and corrective action identified as required.
The RCS hydrostatic test was completed satisfactorily June 21, 1985.
Within the area inspected no violations or deviation were identified.
7.
Plant Tour The inspector toured the control room, reactor auxiliary building, containment, containment annulus, and outside plant areas to observe work activities in progress, housekeeping and tag controls on equipment.
Within the areas inspected no violations or deviations were identifie Nh I
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