IR 05000416/1982050
| ML20055A059 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 06/25/1982 |
| From: | Cantrell F, Scott D, Wagner A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20055A052 | List: |
| References | |
| RTR-NUREG-0660, RTR-NUREG-0737, RTR-NUREG-660, RTR-NUREG-737, TASK-2.F.1, TASK-2.K.1, TASK-3.D.3.3, TASK-TM 50-416-82-50, NUDOCS 8207150438 | |
| Download: ML20055A059 (6) | |
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'o, UNITED STATES
NUCLEAR REGULATORY COMMISSION o
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REGION 11 h
101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303
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Report No. 50-416/82-50 Licensee: Mississippi Power and Light Company Jackson, MS Facility Name: Grand Gulf
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Docket No. 50-416 License No. CPPR-118
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Inspectors:
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A. G. Wagner Date Signed
&NA iArku D. E. Scott
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Date Jrigned
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Approved by: F. S. Cantrell, Sectio p ef, Division of Date S'igned Project and Resident Programs SUMMARY Inspection on May 31 - June 15, 1982 Areas Inspected This routine, announced inspection involved 110 inspector-hours on site in the areas of preoperational test procedure results review, followup of previous enforcement items, inspector followup items, technical specification change review, punch list review, and plant tour.
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Results Of the six areas inspected, no items of noncompliance or deviations were identified.
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PDR ADOCK8207150438 820625
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05000416 O
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DETAILS 1.
Persons Contacted Licensee Employees
- C. K. McCoy, Nuclear Plant Manager
- T. E. Reaves, Jr., Manager Quality Assurance
- J. W. Yelverton, Site QA Manager
- M. A. Lacey, Quality Assurance Supervisor
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J. C. Roberts, Startup Supervisor A. S. McCurdy, Technical Superintendent R. V. Moomaw, I&C Superintendent G. A. Johnson, Operations Superintendent Other licensee employees contacted included operators.
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on June 15, 1982, with those persons indicated in paragraph 1 above. The licensee had no comments regarding the inspection findings.
3.
Licensee Action on Previous Inspection Findings a.
(Closed) Violation 416/82-28-04 - The inspector has reviewed the corrective actions described by the licensee in their letter AECM 82/236 of May 26, 1982.
The inspector verified the incorporation of corrections made to cor rect the specific errors found in the completed preoperational test procedures. There are no further questions. This item is closed.
b.
(Closed) Violation 416/82-13-02 - The inspector has reviewed the corrective actions described by the licensee in their letter AECM 82/92 of March 16, 1982. An audit of the revised procedure was made to ensure.that they were satisfactorily performed after revision and that further revision is not required. The procedures reviewed were 06-IC-1C71-R-010, Rev. 1, Turbine Stop Valve Closure Time Response; 06-IC-1C71-R-007, Rev. O, Turbine Control Valve Time Responce; 06-IC-1B21-R-003, Rev. 2, Reactor Vessel Water Level Response (HPCS). There are no further questions. This item is closed.
c.
(Closed) Violation 416/81-56-03 - The licensee has completed a review of all preoperational tests started at the time this violation was identified. The review identified areas in which previous test results were or could have been invalidated by system run-in activities. The specific areas were retested.
In some cases the entire test was repeated. The licensee has provide the resident inspector a copy of
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the review results. These results are included in the individual system test logs. The test logs are included in the completed test procedure release package which are reviewed by the NRC. There are no further questions. This item is closed.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Inspector Follow-up Items
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a.
(Closed) Open Items 416/81-13-04, 416/81-25-03 and 416/82-40-05. The inspector has reviewed the master and individual system valve lineups to audit the inclusion of plant root valves. A verification was performed on the valve lineups for portions of the following systems:
Nuclear Boiler, Low Pressure Core Spray, Residual Heat Removal System, High Pressure Core Spray and Standby Liquid Control. This verification checked the system Operating Instruction valve lineup against the system drawing. The licensee has instituted a long term program to include the root valves on system drawings. There are no further questions. This item is closed.
b.
(Closed)OpenItem 416/82-28-03 - The inspector verified that the licensee has removed the startup strainers from the ECCS pumps suction lines. There are no further questions. This item is closed.
c.
(Closed) Open Item 416/82-28-01 - The inspector has reviewed the revision of the open vessel plateau test. The revision has removed the requirement for performance of a cold recirculation loop valve test.
There are no further questions. This item is closed.
d.
(Closed)OpenItem 416/82-28-06 - The resident inspector and Region II personnel have reviewed a revised phase I system punch list. This list was derived from an additional review of preoperational test procedure results. The licensee has stated that any additional operational comments observed during testing will be added to Appendix III testing conditions. There are no further questions. This item is closed.
e.
(Closed) Open Item 416/82-40-02 - The inspector reviewed an operations dept. memo which formally named a directive coordinator to remove any
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confusion over the specific assignment. There are no further l
questions. This item is closed.
f.
(Closed) Open Item 416/81-32-03 - The inspector reviewed plant administrative procedure 07-S-01-2 revision 7 which has removed the requirement for designation of LCO's by maintenance personnel. The responsibility for identifying LC0's is included in the procedure for
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the conduct of operations. There are no further questions. This item
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is close.
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g.
(Closed) Open Item 416/82-13-04 - The inspector has reviewed a Temporary Change Notice to plant administrative procedure 01-S-02-2.
This notice defines a minor change. The definition is consistent with ANSI 18.7-1976. There are no further questions. This item is closed.
h.
(Closed) Open Item 416/82-28-05 - The inspector has reviewed the correction of the administrative errors by TCN incorporation. There are no further questions. This item is closed.
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(Closed) Open Item 416/82-18-03 - The inspector has reviewed revision 5 to plant administrative procedure 07-5-01-6.
This revised procedure
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defines the review responsibilities for the personnel signing-off for review of maintenance procedures. This item is closed.
6.
Technical Specification Review The inspector has reviewed the periodic updates of the proposed technical specification. There were no significant comments as a result of the review, 7.
Preoperational Test Results Review The following completed preoperational test procedures were reviewed for conformance with Grand Gulf Startup Manual chapters 5000 and 7000, FSAR Chapter 14 and Regulatory Guide 1.68.
a.
1M41PT01, Containment Cooling System, approved 6-10-82.
b.
IP45AT01, Drywell Floor and equipment Drain System, approved 6-10-82.
c.
IN19AT01, Condensate System, approved 6-11-82.
d.
IP53PT02, Loss of Air Test, approved 6-10-82.
The inspector had no comments or findings.
8.
Grand Gulf Punchlist Review The inspectors have at various times reviewed the punchlist. This review was conducted to review the item milestone designations made by the licensee. Comments were discussed and resolved with the licensee at the time of the review.
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9.
Plant Tour The inspectors toured portions of the control building, auxiliary building, l
containment and refueling floor. The inspector observed the following l
activities in progress: housekeeping; equipment preservation; temporary
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alterations, maintenance, communications equipment controls and fuel movements into the containment. The following observations were made:
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a.
It was noted that the operators in the containment and refueling were not using procedures for operating the fuel handling cranes and the transfer tube during fuel transfer. The inspector was informed that it was not felt necessary to have a prueedure in hand for frequent repetitive evolutions. The inspector questioned the availability of system operating instructions in the event that questions or problems may arise. The shift superintendent agreed that they should be available and had copies made available for operator use prior to the inspector leaving the area.
b.
It was noted that the containment, refueling floor and hydraulic
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control unit areas were particularly dirty. This observation was made on the basis of evaluating a plant ready to load fuel. An NRC Region II manager was informed that a plan was being implemented to ensure adequate cleanliness prior to fuel load.
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10. TMI Task Action Plan Implementation A verification was conducted of the actions implementing the requirements of the TMI Task Action Plan. These requirements are delineated in NUREG 0660 and 0737. The licensee has responded to the NRC by letters AECM 81/387 on October 12, 1981, AECM 81/153 of June 12, 1981 and AECM 81/276 of August 19, 1981 describing the implementation or providing an implementing procedure for the plan item. The NRC staff has reviewed the responses and have provided evaluations in NUREG 0831, Safety Evaluation related to the Operation of Grand Gulf Nuclear Station, Units 1 and 2 (SER). The following items were reviewed with comments as noted:
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a.
II.f.1.2.d Containment Pressure
The inspector verified the installation of containment pressure indication in the control room. This item is closed.
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b.
II.F.1.2.e Containment Water Level The inspector verified the installation of containment water level indication in the control room. This item is closed.
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II.F.1.2.f Containment Hydrogen The inspector verified the installation of containment hydrogen indication by the control room. This item is closed.
d.
II.K.1.22 Auxiliary Heat Removal System
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The inspector has verified the installation _of the automatic shif t of the RCIC pump suction on CST low level or Stppression Pool high level.
This was accomplished in review of the completed preoperational test.
This item is closed.
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e.
II.K.1.5 Review E.S.F. Valves (1) The inspector has reviewed the revision to plant administrative procedure 01-S-06-1, Rev. I which requires the use of miniature tags on control panels. This item is closed.
(2) The inspector has reviewed TCN's to plant administrative procedures 01-5-07-1 and 01-5-06-2 which require surveillance testing and maintenance procedures to include provisions to ensure proper valve alignments for engineered safety feature valves upon return to normal. This item is closed.
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(3) The inspector has reviewed changes to plant administrative procedure 01-S-06-2 which require the following actions.
(a) When possible, Operations will perform a functional test or Surveillance Operability Test following maintenance on any safety-related system. When such tests are not possible, a complete valve and electrical lineup will be performed within the tagged boundary and a partial functional test will be performed where possible to provide assurance that systems are in fact functional after maintenance.
(b) During periodic tours, Operators and Supervisory personnel will conduct spot checks of fluid system and electrical line-ups.
(c) System line-up changes, other than those covered by step-to-step procedures will be logged and abnormal line-ups will be covered during shift turnover.
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II.K.1.22 Auxiliary Heat Removal System
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The inspector reviewed the completed Reactor Core Isolation Cooling (
(RCIC) preoperational test 1E51PT01. The installation of the automatic transfer modification was verified by the test results review. The
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modification shifts the RCIC pump suction from the condensate water storage tank (CST) to the suppression pool upon low CST level or high suppression pool level. This item is closed.
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III.D.3.3 Improve Inplant Radiation Monitoring
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The inspector reviewed the licensees program and training with the Region 11 radie ion protection specialist and reviewed the implementing ij.
procedure. This item is closed.
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11. Licensee Identified Items
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(Closed) Item 416/CDR-82/06 Reactor Water Level Transmitters. Region II was informed of a potentially reportable deficiency (10 CFR 50.55(e)). This u
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item involved the response time of the reactor water level transmitters.
l The inspector reviewed a subsequent evaluation by the licensee which determined the item to be non-reportable. This item is closed.
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