IR 05000416/1982004
| ML20041A824 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 01/25/1982 |
| From: | Hardin A, Wagner A NRC, NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20041A813 | List: |
| References | |
| 50-416-82-04, 50-416-82-4, IEB-79-24, IEB-80-17, NUDOCS 8202220557 | |
| Download: ML20041A824 (5) | |
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UNITED STA.TES
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NUCLEAR REGULATO'iY COMMISSION o
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REGION 11
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.101 MARIETTA ST.,14.W., SUITE 3100
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ATLANTA, GEORGIA 30303.-
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Licensee: !!ississippi Power and Light Company
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Jackson,!!!ssissippi-l'
3acility. flame: Grand Gulf
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-ITocket_ tkn 50-416 '
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(License flo.. CPPR-118 -
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A.'G. Wagner (!
Datq Signed
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Soproved by:
e-Austin Hardin, Acting Sef: tion Chief, Division of Date ' Signed Resident and Reactor Project Inspection
'SIM1ARY J
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Inspection on December 16, 1981 - January 11, 1982
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Areas I'nspected This routine announced inspection involved 50 inspector-hou;s en site in the areas 6f followup of previous enforcement and unresolved ite'n.s, preoperational test supervisor qualifications and' plant tour.
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Results t
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Of the 3 areas inspected, no items of noncor1pliance or dqviations were identi-fied.
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DETAILS
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Persons Contacted i
Licensee Employees i
- C. K. McCoy, Plant Manager
' T. H. Cloninger, Assistant Site fianager
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- C.~ R. Hutchinson, Startup Manager
- J. W. Yelverton, Quality Assurance Supervisor
- J. C. Roberts, Startup fianager
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- L. F. Daughtery, Plant Quality AH. A. Lacey, Quality Assurance. Engineer
- J. C. Bell, Quality Assurance. Engineer D. Webster, Licensing Engineer
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G. Lee, Training Supervisor
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General Elect"ic M. G. Farschon, Site Operations Manager
- Attended exit interview 2.
Exit Interview The inspection scope and firidings were su.mmarized on January.11, 1982 with those persons indicated in paragraph 1 above. The licensee had no comments regarding the inspection findings.
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3.
Licensee Action on Previous Inspection Eindings a
(Closed) Violation (416/81-31-01)s Failure to follow procedures lip &L letter fio. AECf1 81/378 dated October 2,1981, has been reviewed and determined to be acceptable by Region II. The reyised administrative procedure 01-5-04-4 was reviewed to verify the minimum acceptable examination score was corrected.
The training information~~ notices issued to all personnel previously attending General Employee Training were reviewed to assure that all omitted topics were included. There are no further questions concerning this item. This iten is closed.
(Closed) Violation (416/81-22-02) Inadequate QA training.
Another' audit was conducted of QA indoctrination status maintained by station section supervisors. The audit revealed that the status is being maintained as described MP&L letter AECM 81/280 dated August 4,1981.
Plant Quality and Field' Quality Assurance have conducted reviews of the QA training included in General employee Training.
They are in agreement that the lesson plans includes all required QA training. The inspector reviewed the lesson plan for the QA portion of general employee training to ensure previously identified weak areas were discussed. There are no further questions.
This item is closed.
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2 (0 pen) Unresolved Item (416/81-10-14) The inspector reviewed the status of this item. The FSAR section 9.3.5.3.2 has not been updated to reflect the enclosure status of the Standby Liquid Control system.
This item remains open.
(0 pen) Unresolved Item (416/81-13-01 and 416/81-13-02) The instrument air preoperational test has not been revised to reflect the requirements for vibration monitoring as described in the FSAR paragraph 14.2.12.1.59. 6.1 (b)(3) and the testing requirements contained in Regulatory Guide 1.80, June 1974, paragraph c.5, C.6 and C.7.
This item remains open.
(0 pen) Unresolved Item (416/81-15-04) The inspector reviewed the status of this item.
The licensee has utilized additional training services of the
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Nuclear Steam Supplier to answer or resolve questions pertaining to plant transient analysis. The licensee has not however determined the need to revise the FSAR to provide plant specific transient analysis curves. There does not exist a formal feedback method for correction of FSAR errors.
This item remains open.
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(0 pen) Unresolved. Item (416/81-22-03) The inspector reviewed the status of i
this item.
No action has been taken by the licensee concerning this item.
This item remains open.
(Closed) Unresolved Item (416/81-25-01) The licensee has provided updated
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copies of plant system P&ID's in Amendment 52 of the Final Safety Analysis Report.- An installation verification will be performed using the revised P&ID's as required by the NRC Inspection Program. Additional identified discrepancies will be documented by seperate report. There are no further questions. This item is closed.
(Closed) Unresolved Item (416/81-32-04) The inspector reviewed the revised procedure 01-5-02-02.
The revision incorporated the requirements for System Operating Instructions, Alarm Response Instructions, Maintenance Procedures (Safety Related) and Radiation Procedures as will be required by imple-mentation of the proposed technical specifications. There are no further questions.
This item is closed.
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Unresolved Items Unresolved items were not identified during this inspection.
5.
IE Bulletins The inspector reviewed the status of the following IE Bulletins.
a.
(Closed) IE Bulletin 80-17, " Failure of 76 of 185 control rods to fully insert during a scram at a BWR."
This bulletin was sent to the licensee for information only.
The NRC conducted a generic study and
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sent to flississippi Power & Light Company the Generic Safety Evaluation Report, BWR Scram Discharge System dated December 1,1980. Mississippi Power and Light Company responded to an NRC inquiry on their method of
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complying with the generic safety evaluation criteria by letter AECM 81/34 of September 2, 1981.
The method described was accepted by the Office of Nuclear Reactor Regulation in paragraph 4.6 of the Safety Evaluation Report related to the operation of Grand Gulf Nuclear Station Units 1 and 2 issued September 1981. This item is closed.
b.
(Closed) IE Bulletin 79-24, Freeze Lines.
The licensee's response by letter No. AECH 79-124 dated October 31, 1979 states that an evaluation has been perfomed.
The current design of the plant heating equipment provides adequate protection from freezing.
It was reported that several sensing lines in the ultimate heat sink between the concrete slab and top of the water level would be exposed to outside air. A subsequent review by the licensee showed that the water level will be maintained above the slab level thus keeping the sensing line from being exposed.
Thus freeze protection is not required for these lines.
This item is closed.
6.
Licensee Identified Item a.
(Closed) CDR 77-13.(416/78-01-01) SRV Control Valves. On October 7, 1977, the licensee notified IE:II of a 50.55(e) item concerning the control circuits for the safety relief valves. The final report was submitted on October 30, 1981.
The report has been reviewed and determined to be acceptable by IE:II. The design changes were discussed with the NRC staff in Bethesda, Maryland, on February 8, 1980.
The staff has completed its review of the proposed changes and finds them acceptable as stated in the safety evaluation report related to the operation of Grand Gulf Nuclear Station Units 1 and 2, supple-ment No.1 paragraph 6.2.1.8.2.
The inspector held discussions with responsible licensee and/or contractor representatives and reviewed supporting documentation to verify that the corrective actions identified in the report have been completed.
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(Closed) CDR 81-34, Incorrect Reactor Water Level Measuring Devices.
On August 23, 1981, the licensee notified IE:RII of a 50.55(e) item concerning incorrect reactor vessel water level transmitters and trip units. The report has been reviewed and determined to be acceptable by IE:II. The inspector held discussions with responsible licensee and/or contractor representatives and reviewed supporting documentation to verify that the corrective actions identified in the report have been completed.
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(Closed) CDR81-40, Presray Inflatable Seals for Personnel Airlocks. On October 8,1981, the licensee, notified IE:II of a 50.55(e) item concerning potential cracking of inflatable seals manufactured by Presray.
The report has been reviewed and determined to be acceptable by IE:II. The inspector held discussions with responsible licensee and/or contractor representatives and reviewed supporting documentation to verify that the corrective actions identified in the report have been complete r
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7.
Inspector Followup Items a.
(Closed)OpenItem 416/81-36-01. The inspector reviewed the change to the checkout and turnover manual which specifies the proper method of voiding an approved construction work permit. There are no further questions concerning this item. This item is closed.
b.
(Closed) Open Item (416/81-25-02) The inspector reviewed FSAR amend-ment 51 which removed the incorrect reference to the High Pressure Core Spray turbine. There are no further questions concerning this item.
This item is closed.
c.
(Closed) Open Item (416/80-24-04) This item is considered by the licensee to be an isolated occurrence of an oversight on the part of the QC representative. The incident was detected by QC during final review to meet their programatic requirements. The inspector has not detected any similar items during subsequent inspections. The inspector concurs that this appears to be an isolated occurrence.
There are no further questions concerning this item.
This item is closed.
d.
(Closed) Open Item (416/81-10-13) The inspector reviewed the test change notice which incorporated the testing for the Standby Liquid Control Heat Tracing.
There are no further questions concerning this item.
This item is closed.
8.
Plant Tour The inspector toured portions of the control building, auxiliary building and containment.
The inspector observed the work and operations in progress in the toured areas.
No violations or deviations were identified for the areas inspected.
9.
Area of Worker Concern A review of qualific'ations for ten startup test personnel was conducted.
the review was to verify compliance with Grand Gulf Startup 11anual paragraph 4.6.1.
The review was performed on the records of ten startup personnel.
Of the personnel selected, seven were qualified and certified as preoperational or startup test supervisors. Three of the personnel are in a training status and reportedly not performing safety-related functions. As they are under the direct supervision of a qualified preoperational test supervisor.
No violations or deviations were identified for the areas inspected.
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