ML20214G189
| ML20214G189 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 11/14/1986 |
| From: | Conway R GEORGIA POWER CO. |
| To: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| 0529H, 529H, SL-1578, NUDOCS 8611260005 | |
| Download: ML20214G189 (7) | |
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Geortpa Poe Company 333 Piedmont Avenue A!;anta Georqa 30308 Te!cphone 404 526-6724 Ma t:nq A:tf ess Post Ottce Bos 4545 AIMnta Georg a 30302 uG tigy 17 All ; 3R R.E.Conway Ser Vre Present SL-1578 0529H November 14, 1986 United States Nuclear Regulatory Commission Region II Suite 2900 101 Marietta Street, Northwest Atlanta, Georgia 30323 NRC DOCKET 50-424 CONSTRUCTION PERMIT NUMBER CPPR-1080 VOGTLE ELECTRICAL GENERATING PLANT - UNIT 1 STATUS FOR PUEL LOADING Attention: Dr. J. Nelson 3 race:
Georgia Power Company (GPC) is nearing completion of
- design, construction, and testing of the Vogtle Electric Generating Plant Unit 1 (VEGP-1).
These activities have been or will be completed in accordance
-with representations and descriptions contained in the Final Safety Analysis Report (FSAR) and supporting documents and information provided in this letter.
A detailed assessment of the status of the work activities necessary to support fuel load and low power / power ascension testing at VEGP-1 has been completed.
This assessment is in addition to the extensive evaluation made of our Vogtle program by GPC in the detailed implementation of our Readiness Review Program.
Consistent with the practices of other recent licensees, it, is anticipated that several VEGP-1 construction, preoperational testing, and post-test review activities that are not directly related or prerequisites to fuel load will be completed after fuel load.
We will implement appropriate radiation detection, security lock down, and surveillance procedures.
GPC's evaluation of work which will not be completed prior to fuel load will ausure that these activities do not affect the ability of VEGP-1 to safely conduct fuel loading nor preclude the issuance of an operating licenso.
The following attachments contain lists of activities or tests that may not be completed at fuel load:.
Construction Activities.
Preoperational Tests Some work items on these attachments may be partially completed or dispositioned prior to fuel load.
8611260005 061114I PDR ADOCK 0S000424 A
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Geo giaPower1 Dr. J. Nelson Grace, Director November 14, 1986 Page Two Other items (e.g.,. outstanding construction items, required hardware modifications, and test exceptions disclosed during preoperational test and inspections) classified as restraints to fuel load will be closed or properly dispositioned prior to commencement of fuel load.
Items classified ar restraints to any of Operational Modes 5 through I will be closed or dispositioned before operation in such mode is commenced.
Procedures for operation in ~ Mode 6 are essentially written and approved.
Similarly, procedures required for operation of VEGP-1 in each mode of operation will be written and approved prior to entry into the operational mode for which the procedure is required.
The GPC Safety Review Board has conducted a review of, and concurred in, the status of readiness for fuel load as reflected in this letter and concluded that the commitments and statements made in this letter will not adversely affect the health and safety of the public.
The design, construction, and testing required as prerequisites for fuel load should be completed prior to the end of December, 1986.
Our scheduled completion date for VEGP-1 remains December 15, 1986.
As described above, prerequisites for other modes will be completed prior to ascension to those modes.
GPC intends to file a Facility Completion letter and a Technical Specificationc certification letter in early December as the final documentation prior to issuance of a Low Power Operating Licer.ne.
Should you have any comments regarding our status for fuel load,-please contact me at your convenience.
Sincerely, R. E. Conway REC:ht Enclosures
Georgia Power d Dr. J. Nelson Grace, Director November 14, 1986 Page Three c:
U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C.
20555 H. G. Baker D. R. Altman L. T. Gucwa J. P. O'Reilly P. R. Bemis C. W. Hayes G. F. Head J. A. Bailey G. A..McCatley-P. D. Rice O. Batum R. W.~McManus R. H. Pinson G. Bockhold Sr. Resident (NRC)
C. W. Whitney C.
E. Belflower C. C. Garnett (OPC)
B. M. Guthrie J. F. D'Amico J. E. Joiner (TSLA)
D. E. Dutton W. D. Drinkard D. Feig (GANE)
R. A. Thomas E. D. Groover NORMS t
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ATTACHMENT 1 VOGTLE ELECTRIC GENERATING PLANT - UNIT 1 CONSTRUCTION ACTIVITIES THAT MAY NOT BE COMPLETED AT FUEL LOADING Activity Justification Estimated Completed Penetration seals On-going construction Seals will be completed I
and testing activities or dispositioned prior restrict access for completion to the operational mode l
of seals.
for which required.
Insulation installation /
Access to piping without Insulation will be rework in;ulation is necessary completed or dispositioned for hanger rework, prior to the operational testing requirements mode for which required, and freeze protection heat tracing.
Miscellaneous punchlist On-going work not related Fork will be completed or items to Mode 6 operation.
dispositioned prior to the operational mode for which l
required.
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ATTACHMENT 2 VOGTLE ELECTRIC GENERATING PLANT - UNIT 1 PREOPERATIONAL TESTS THAT MAY NOT BE COMPLETED AT FUEL LOADING DESCRIPTION OF JUSTIFICATION COMPLETION PROCEDURE NUMBER AND NAME DEFERRED TESTING
- (SEE Page 3)
BY 1-3BB-05: Pressurizer Pressure Power Operated Relief
- 1 Mode 2 and Level Control System Valve stroke times at Temperature and Pressure. Pressurizer Level transmitters were respanned since Hot Functional Tests.
1-3BB-04:
Reactor Coolant System Retest repaired valves
- 2 Mode 2 Leak Rate Preoperational Test 1-3BB-09: Resistance Temperature-Cross calibration Loop 3
- 3 Mode 2 Detector Cross Calibration Resistance Temperature Detectors, Measure Resistance Temperature Detector lead insulation resistance.
1-3BB-10: -Resistance Temperature Retest Resistance
- 4 Mode 2 Detector Bypass Preoperational Test Temperature Detector Bypass 1-3AL-03: -Auxiliary.Peedwater Actuation starts of
- 5 Mode 2 System Testing Motor Driven and Turbine during Hot Functional Tests Driven pumps, flow to pressurized Steam Generator 1-3AB-01: Main Steam Main-Steam Isolation Valve
~+6 Mode 2 System hot stroke time testing after rework. Test post Fuel Load.
Startup test procedure 1-500-4 1 of 3
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1 DESCRIPTION OF JUSTIFICATION COMPLETION PROCEDURE NUMBER AND NAME DEFERRED TESTING
- (SEE Page 3)
BY 1-3SD-2:
Digical Radiation Preoperational Testing
- 7 Per Technical Monitoring System (Communication of all radiation monitors Specification console) not required for Fuel Load requirements (Mode 6).
Technical Specifications may
[
not be completed.
l 1-30K-01: Fire Detection System Fire Detection System Not Safety-Related Commercial in the Turbine Building System Operation I
l l-300-14:
Initial Turbine Roll Turbine sequential Not Safety-Related Commercial tripping System Operation' l-3SO-01 : Metal Impact Monitor Impact Retesting to
- 8 Mode 5 provide baseline systems responses XXXX-Raawaste Systems Testing Listed Radwaste Solid-Upon i
in FSAR ification Building. completion of i
Construction permanent l
deferred.
systems Contractor described in Facilities to be the FSAR utilized High Efficiency Particulate Testing of Filter Testing will be Mode 6 Absorber / Charcoal Testing for package performed under Safety Heating Ventilating and Air Surveillance Test systems Conditioning Systems for Safety Related systems Commercial and vendor test Operation for Non-Safety Non-safety Related systems systems i
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JUSTIFICATION FOR DEFERRED TESTING 1.
Power Operated Relief Valves failed preoperational testing acceptance during Hot Functional Testing.
Valves were reworked after Hot Functional Testing and require hot plant conditions for retest.
Level instrumentation successfully passed preoperational
- test, but instruments were respanned after Hot Functional Testing.
The Pressurizer Level Control System requires dynamic tuning at hot plant conditions.
2.
Valve leakage was identified during Hot Functional Testing.
The valves were repaired and the final leak rate test is scheduled as a startup test 1-5BB-01.
3.
Cross calibration comparison will be done on Reactor Vessel Level Indication System Resistance Temperature Detectors that were missed during Hot Functional Testing.
Additionally, some of the Resistance Temperature Detector cables were replaced due to design reevaluation.
Resistance Temperature Detector insulation resistance will be measured at normal pressure and temperature for those Resistance Temperature Detectors that had cables replaced.
4.
Resistance Temperature Detector Bypass will be retested at normal temperature and pressure as a result of new orifice design since Hot Functional Testing.
5.
Actuation starts will be tested at normal pressure and temperature because of flow orifice and flow control and valve redesign since Hot Functional Testing.
6.
Main Steam Isolation Valves were successful.ly hot stroked during hot functional.
Due to rework of the Main Steam Isolation Valve solenoids, the valves will be hot stroked during the Start-Up phase.
7.
All testing of radiation monitors required per Technical Specifications for Mode 6 and at all times will be completed.
i 8.
During preoparational testing, the system has demonstrated impact i
response.
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