IR 05000416/1981036
| ML20031F902 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 09/30/1981 |
| From: | Cantrell F, Wagner A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20031F896 | List: |
| References | |
| 50-416-81-36, NUDOCS 8110200530 | |
| Download: ML20031F902 (6) | |
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UNITED STATES e
NUCLEAR REGULATORY COMMISSION
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E REGION 11 I
101 MARIETTA ST., NYl SUITE 3100 q
ATLANTA, GEORGIA 30303 g*****&
Report No. 50-416/81-36 Licensee: flississippi Power and Light Company Jackson, its 39205 Facility Name: Grand Gulf Docket No. 50-416 License No. CPPR-118 Inspector:
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g.G. Wagner Date Signed Approved by:
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F. Cantrell, Section Chief RPS 18 Date Signed Suit!!ARY
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Inspection on August 15 to September 15, 1981 Areas Inspected This routine, unannounced inspection involved 100 inspector-hours on site in the areas of system turnover review, system jurisdictional controls, quality assurance monitoring, quality assurance monitoring checks, preoperational test schedule, technical specification review, fine prevention protection, pre-operations test witnessing, temporary alteration review, preparations for fuel receipt, inspector followup item and plant tour.
Resul ts l
l Of the 12 areas inspected, no violations or deviations were identified.
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DETAILS 1.
Persons Contacted Licensee Employees
- G. B. Rogers, Site Manager
- C. K. McCod, Plant flanager
- C. R. Hutchinson, Startup Manager
- J. W. Yelverton, Quality As:,ance Supervisor
- J. C. Roberts, Startup Supervisor
- D. L. Hunt, Plant Quality Supervisor
- J. C. Bell, Quality Assurance Engineer
- L. C. Eichenberger, Test Supervisor R. A. Ambrosino, Nuclear Support flanager A. S. McCurdy, Technical Superintendent W. R. Paterson, Reactor Supervisor J. D. Bailey, Plant Quality Other Organizations
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on September 15, 1981 with those persons indicated in paragraph 1 above. The inspector discussed the reporting requirements of 10 CFR 70.52.
The licensee had no questions regarding the reporting requirements. The licensee had no comments regarding the inspection findings.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
System Turnover Reviews The turnover packages for positions of the high pressure core spray diesel generator system and control rod drive system rod control information system were reviewed for the requirements of Grand Gulf Startup Manual Chapter 7000, paragraph 4.1.4 and Bechtel Checkout and Turnover Organization llanual chapter 4 section 16.
No violations or deviations were identified within the areas inspecte.
6.
System Jurisdictional Controls
Portions of the Nuclear Boiler System, Recirculation System, Standby Diesel Genertor and Residual Heat Removal System were visually spot checked to verify system tagging had been accanplished as required by the Grand Gulf Startup itanual Chapter 5000, paragraph 4.4.
It was noted that a Bechtel construction safety tag was hung on wiring for valve B21F022B. The system had been turned over to the Grand Gulf startup organization. The safety tag was placed during the processing of construction work permit CWP-1C71(2)-20 on July 7,1981 for valve repairs.
The CWP was then subsequently voided by the Bechtel Construction Organization without clearing the safety tag.
Voiding of CWP's is not specifically authorized by Bechtel Checkout and Turnover manual. This is an isolated occurance and is documented by Bechtel Condition Report.
This item will be reviewed during a subsequent inspection. Open item 416/81-36-01.
It was also noted that there were three Bechtel checkout and turnover jurisdictional blue tags located in 4.16 KV switchgear control cabinet.
They were attached to a portion of the systen turned over to the Grand Gulf startup organization. The tags were removed.
This is considered an isolated case in which the test supervisor terminated employment during the system turnover process.
No violations or deviations were identified within the areas inspected.
7.
Quality Assurance Itonitoring The inspector reviewed the quality assurance monitoring activities in the preoperational test area. The activities were reviewed for conformance with Quality Assurance Procedures Manual Chapter 18.20 and the following reports were reviewed.
a.
C.A.R.
316 - Protective Tagging System b.
C.A.R.
327 - Startup of Stundby Service Water c.
C.A.R.
361 - Temporary Change Notices No violations or deviations were identified within the areas inspected.
8.
Quality Assurance Surveillance Checks The inspector eitnessed the conduct of surveillance check activities associated with preoperational testing.
The activities of the QA inspectors were monitored to verify compliance with Quality Assurance Procedures ibnual Chapter 18.20 and Administrative Procedures 15-S-01-5.
The following test activity monitoring was observed:
a.
1E12PT01 - RHR Preoperational test.
b.
1C885001 - Vibration Monitoring Preoperational Test
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The inspector discussed his concerns about the large number of test change notices and test exceptions that have been processed for the RHR pre-operational test with senior licensee management.
The abuse of these testing controls could make technical and administrative review of the procedures difficult to impossible.
No violations or deviations were identified within the areas inspected.
9.
Preoperational Test Schedule The inspector reviewed the revised testing schedule dated September 8,1981.
The schedule appeared to reflect the current status of testing and the latest project schedule for completion of testing.
No violations or deviations were noted within the inspected.
10.
Technical Specification Review The inspector conducted a review of the facility draft technical specifi-cations.
These specifications were provided by the office of fluclear Reactor Regulation (NRR). The review comments were forwarded to the NRC Region II office.
The comments will be incorporated with any regional review comments and sent to the appropriate NRR office for resolution with the licensee during a subsequent review meeting.
11.
Fire Prevention and Protection An inspection was made of the control room an the cable spreading room El. 190. The inspection included a review of installed fire protection equipment. The inspector reviewed the records for cable penetrations.
IBAA OT35,1BAA OT36 and 1BAA OT34 to verify that they indicate that the seal material was tested and rartified that it is not flamable. There were no formal fire protectinn # ng held since the last inspection of this area.
No violations or deviations were identified in the areas inspected.
12.
Preoperational Test Witnessing The inspector witnessed the conduct of portions of preoperational test 1C41PT01 Standby Liquid Control System Preoperational Test. The test was observed for conformance with Grand Gulf Startup Manual Chapter 5000 and 7000. The inspector observed the standby liquid control system tank vent during the inspection and no problems were indicated nor does it appear that potential problems will occur in the future. Minor coninents were discussed with senior licensee management.
No violations or deviations were identified within the area inspecte,
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13. Temporary Alteration Review The inspector audited the following temporary alterations. The audit verified compliance with plant Administrative Procedure 01-S-6-3 Control of System Temporary Alterations. Minor comments were discussed with senior licensee management.
a.
Log 810091 for B21-N691A b.
Log 810091 for B21-N691E c.
Log 810139 for B31-N680A d.
Log 810438 for B21-N681A e.
Log 810436 for P75 - D/G panel 852 No violations or deviations were identified for the areas inspected.
14. Preparations for Fuel Receipt The inspector reviewed the following Grand Gulf Nuclear Station procedures for compliance with flississippi Power and Light Company's application for Special Nuclear Material (SNil), license amendments 1, 2 and 3 and U. S. NRC flaterial License SNM-1882. The review included specific storage requirements, control for environmental protection, verification of documentation / records and reporting requirements which were also discussed at the exit interview. The procedures reviewed include:
09-S-02-100 Criticality Rules 09-S-02-104 New Fuel Inspection and Channeling 09-S-02-104 Inspection and Storage of New Fuel.
09-S-01-106 Shipment of New Fuel 09-5-01-101 Receiving New Fuel 09-S-02-105 Storage of New Fuel The following comments were noted during the review.
a.
The procedures do not include provisions for draining the fuel storage area as required by SfH 1882 b.
SNM-1882 does not authorize fuel storage in any type of temporary storage rack as alluded to in 09-S-02-105 c.
Procedure 09-S-02-105 does not specify provisions for control in the event of outside storage as outlined in SNM license application amendment 3 dated April 27, 1981.
d.
Procedure 09-S-01-101 does not require a formally defined inspection of fuel shipment for damage prior to unloading as required by ANSI N 45.2.2-1972 paragraph 5.2.2.
e.
Procedure 09-S-02-100 does not appear to fully incorporate requirements for keeping fuel protected with a fire retardant
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covering as required by SNM license application amendment 3 dated April 27, 1981.
f.
09-S-02-100 Criticality Rules procedure does not contain requirements for outside stored new fuel as contained in SNM license application amendment 3 dated April 27, 1981.
A senior licensee management representative stated that these items woulb be reviewed and appropriate corrective action taken. These items will be reviewed during a subsequent inspection.
Open item 416/81-36-02.
15.
Inspector Followup Items (Closed) Open item 416/81-03-01.
The startup manual was revised deleting the temporary test operating instruction.
(Closed) Open item 416/81-03-02.
The startup manual was re'tised deleting the temporary test operating instruction.
(Closed) Open item 416/81-03-03.
The startup manual was revised deleting the temporary test operating instruction.
(Closed) Open item 416/81-10-10.
The vibration data requirements for
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IC41PT01 were incorporated into procedure 1C885T01.
(Closed) Open item 416/81-10-06.
The diesel generator voltage and speed measurement requirements were deleted by FSAR Amendment 48. These measurements will be performed during the individual diesel generator j
preoperational test.
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(Closed) Open item (416/80-28-01.
The requirement for the Rod Control and Information System operability was included in the approved procedure.
(Closed) Open item 416/80-28-02.
The requirements for temporary alteration control were included in the approved procedure.
(Closed) Open item 416/80-28-03.
Quantitive or qualitive acceptance criteria was included in the approved procedure.
16.
Plant Tour The inspector toured portions of the control building auxiliary, building and containment. The tours were made at various times.
The inspector observed the work and operations in progress in the toured areas.
The inspector observed construction workmen in area 11 of the containment El.184 with a metal toolbox in cable tray ICATM009.
Bechtel construction processed a condition report. The cable tray and cables were inspected to i,
verify no damage had resulted. The condition report was then closed.
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