ML20211P448
| ML20211P448 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 01/16/1987 |
| From: | Conway R GEORGIA POWER CO. |
| To: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| GN-1335, NUDOCS 8703020368 | |
| Download: ML20211P448 (5) | |
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o Georgia Power Company 333 Piedmont Avenue At:anta Georg,a 30308 Telephorm 404 526 6724 Ma:hng Address Post Off'ce Box 4545 At:anta Georg:a 30302
"""'"#**'^#""
R.E.Conway Sernor Vice President January 16, 1987 k$
6 1
United States Nuclear Regulatory Commission File:
X7BGlt03 Region II - Suite 2900 Log:
GN-133$*C" 101 Marietta Street, Northwest Atlanta, Georgia 30323
Reference:
Unit 1 Statement of Completion and Request for Low Power Operating License, NRC Docket 50-424 Attentio:4:
Dr. J. Nelson Grace By letters dated November 14, 1986, December 22, 1986, January 2, 1987, and January 9, 1987, I advised you of the status regarding activ.Lties at the Vogtle Electric Generating Plant, Unit 1 (VEGP-1).
The purpose of this letter is to provide you an updated status and to advise you that Georgia Power Company has now completed the design, construction, and preoperational testing required for Vogtle Unit 1 fuel loading.
In my status letter of January 2, 1987, we identified 9 areas of "preoperational testing that may not be completed prior to fuel load".
I am pleased to inform you now that all the described testing for fuel loading is complete and further progress has been made in the 9 areas of deferred preoperational testing.
Attachment 1 included herein is a summary of our current status.
We are working and will continue to work these areas to complete them as previously described.
We understand that as of this time, there are still 9 mode related issues contained in the 94300 letter.
We are working with your staff on these items and will resolve them by the required modes.
They are identified on Attachment 2 included herein.
In addition, the remaining open items on inspection reports86-117 and 87-01 will be resolved prior to initial criticality.
Our daily status meetings have been providing your site representatives information in key areas required for fuel loading.
I would like to summarize that status for you as of this time.
The fuel load punchlist has been reduced to 10 items.
Three of these are " field work complete".
The "at all times" and Mode 6 Technical Specifications Surveillances are now complete and the 8703020360 870116 PDR ADOCK 05000424 P
PDR _
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Page Two less than seventy-two hour and "special condition" surveillances have been initiated.
Twenty-nine of twenty-nine systems required for fuel loading have been declared operable.
The startup neutron sources have been installed and the " dunking chamber" startup detectors have been placed into the reactor vessel.
We are ready to load fuel.
We, therefore, request that the commission issue a license permitting commencement of fuel load activity upon completion of NRC inspection activities.
As always, we are prepared to provide any additional information that you may require.
Sincerely, M^
i R. E.
Conway ALM / REC / erd xc:
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. McCarley P.
D. Rice O.
Batum R. W. McManus R.
H.
Pinson G.
Bockhold Sr. Resident (NRC)
C. W. Whitney C.
E.
Belflower D.
D. Smith (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 H.
R.
Denton M. A. Miller (NRC)
V,;
'o ATTACRMENT l' Status Update on Deferred Preoperational Testing 1.
1-300-07.RCS Hot Functional Further progress can not be made until the plant is hot.
2.
1-3SD-01 Digital Radiation Monitoring 1-3SD-02 "Preoperational" portion - Committed
- testing is now complete.
Mode 6 Surveillances - All fifteen Mode 6 detectors' surveil-lances are complete.
Mode 4 Surveillances'- One detector surveillance is complete.
Two are in progress.
Nine remain.
Mode 2 Surveillances - Have not started.
3.
HEPA and Carbon Filter Package Testing Mode 6 - Committed
- testing is now complete.
Mode 4 Surveillances - Both control Room Filter packages are loaded.
Package testing is in progress.
The Piping Penetration Packages are not yet loaded.
Mode 2 - Four of ten filter systems are now loaded.
One system is in the process of loading.
1 4.
1-3GL-04 Piping Penetration Filter Exhaust Mode 4 - The preoperational test is complete except for portions restrained by air balance activities which are now 2/3 complete.
5.
Radwaste System Testing 1-3HB-02 Waste Processing System Liquid 1-3HE-01 Boron Recycle System Further testing has not been performed.
p,,
- - ~
15.
1-3RJ-01 Proteus Computer Preoperational Test Further testing has not been performed.
7.
Breathing Air System Further' testing has not been performed.
8.
1-3RP-03 Post Accident Monitoring System The PROM (Programmable Read Only Memories) modification was, successful.
This preoperational test is now 97% complete.
9.
IFI 424/86-121-02 Inspection Followup Item on NSCW Testing Correspondence GN-1307, dated January 10, 1987, was sent to NRR providing an abstract of the proposed testing.-
- Note:
Committed testing is'that described in reference letters, dated January 2, 1987 and January 9, 1987.
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ATTACHMENT 2 OPEN 94300 LETTER ITEMS 1.
86-65-03 Review final resolution to MSIV coil failure and subsequent retest 2.
86-73-03 Delete use of makeup to VCT during RCS leakage measurements 3.
86-117-09 Correction of discrepancies in RVLIS Surveillance Procedure and followup on vendor recommendations 4.
86-117-31 Corrective action to-assure that key control system allows prompt access to locked rooms and cabinets 5.
86-121-01 NSCW Surveillance Test Procedures 6.
86-02 Determine if any static
'o' ring differential pressure switches are installed for safety-related purposes.
7.
87-08-01 Minor changes to procedure data sheets may change acceptance criteria.
Changes to acceptance criteria are not allowed under a minor change.
8.
CDR 86-130 Main Steam Isolation Valve closure time 9.
II E 1.2 Auxiliary Feedwater System initiation and flow i
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