ML19321A849
| ML19321A849 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 07/03/1980 |
| From: | Houghton T Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8007240287 | |
| Download: ML19321A849 (7) | |
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UNITED STATES Y
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JUL 3 1980 4
Docket Nos.:
50-416/417 APPLICANTS:
Mississippi Power and Light Company Middle South Energy, Inc.
FACILITY:
Grand Gulf Nuclear Station, Units 1 and 2 SUBJELT:
SUk/ARY OF JUNE 25, 1980 MEETING On June 25, 1980 members of the staff and our reviewers from Savannah River Laboratory met with the applicant, Mississippi Power and Light, and his consultants in Gaithersburg, Maryland. The purpose of the meeting was to clarify Instrumentation and Control Systems questions and responses and to discuss the review schedule. lists the attendees and enclosure 2 identifies action items agreed upon during the meeting.
The raeeting provided an extremely valuable and frank exchange of information between our reviewers and the applicant, which will reduce the time neces-sary to complete the review and will allow a more thorough and complete safety evaluation.
CI f
%.m Thomas C. Houghton,(P oject Manager Licensing Branch No.
Division of Licensing
Enclosures:
As stated cc:
See next page l
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Mr. N. L. Stampley Vice President - Production Mississippi Power & Light Company P. O. Box 1640 Jackson, Mississippi 39205 cc: Robert B. McGehee, Esq.
Wise, Carter, Child, Steen & Caraway P. O. Box 651 Jackson, Mississippi 39205 Troy B. Conner, Jr., Esq.
Conner, Moore & Corber 1747 Pennsylvania Avenue, N. W.
Washington, D. C.
20006 Mr. Adrian Zaccaria, Project Engineer
- Grand Gulf Nuclear Station Bechtel Power Corporation Gaithersburg, Maryland 20760 Mr. Alan G. Wagner, Resident Ihsp'e'ct'or P. O. Box 469 Port Gibson, Mississippi 39150 t
e e
MEETING WITH SAVANNAH River /NRC JUNE 25,1980 MP&LCo John D. Richardson G. Cesare Ray Patterson SE J. E. Swan Georgb'Darmohray J. Fray D. J. Robare CuPont, SRP G. W. McManaway C. P. Ross Arthur E. Hadden Bechtel H. M. Brooks D. W. Fouts S. D. Routh J. C. Catlin C. R. Wienke 1
NRC J. Martore T. Dunning T. Houghton l
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MEETING SU"M,RY DISTRIBUTION Docket File J. Stolz NRC PDR
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o NSIC D. Ziemann ye Branch File R. Ma ttson H. Denton R. Schroeder E. Case K. Kniel D. Eisenhut D. Skovhol t R. Purnle G. Knighton T. Novak M. Ernst S. Varga R. Baer e,
T. Ippolito C. Berlinoer R. A. Clark S. Israel R. Reid ACRS (16)
R. Tedesco Attorney, OELD J. Youngblood OIE (3)
A. Schwencer 05D (7)
Chief Lic'ensing Branch #3 Project Manacer T. C. Houghton J. R. Miller Licensino Assistant J. Lee G. Lainas Receptionist D. Crutchfield TERA Chief, Systemic Evaluation Program Branch J. LeDoux, IAE Chief, Ooerating Reactors Assessment Branch R. Vollmer I&E Headnuarters R. Bosnak IAE Region !
F. Schauer
!&E Reaion !!
R. E. Jackson I&E Region !!!
G. Lear
!&E Region IV V. Hoonan I&E Region V
- 5. Pawlicki V. Benaraya NRC Particioants:
Z. Rosztoczy J. Martore W. Haass T. Dunning D. Muller T. Houghton l
R. Ballard W. Regan J. D. Sal tzman D. Ross P. Check R. Satterfield O. Parr bcc:
Aoplicant & Service list F. Rosa W. Butler W. Kreger R. W. Houston T. Murphy W. Gammill L. Rubenstein T. Soets Chief, Core Performance Branch ACTION ITEMS FROM JUNE 25, 1980 MP&L/NRC MEETING 1.
To facilitate the Savannah River Laboratory (SRL) review, an advance copy of the ICSB responses will be sent to NRC and SRL by mid-July.
(The official amendment will be submitted on July 31,1980.)
2.
Savannah River Laboratory expects to complete ICSB SER input by September.
3.
.SRL will send a list of specific comments to amplify previous questions to the NRC during the week of June 30, 1980.
4.
A general problem with responses to date is that statements of complicance are incomplete.
5.
MP&L needs an introductory paragraph that explains Table 1-3 and how they address compliance to certain standards, Reg. Guides and GDC.
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NRC/SRL MEETING-FSAR CHAPTER 7 4
Specific Question Action Items T
i 031.55-a)
Response in 7.2.2.1.2.2 is inaccurate.
Recommend change to statement of compliance with GDC 12; due to reactor design,
. reference appropriate Chapter 4 section.
b)
GDC 25 for Rod Pattern Control Portion of RC&IS should be i
discussed - reference to 7.6.
c) 7.2 address of GDC 25 should be revised.
031.69 - a)
Revise response (211.11) to say that setpoints will be set
'(211.11) high enough initially to avoid inadvertent trip.
Based on
. review of tech specs. this trip may be deleted.
031.48 - a)
Item 2 - Revise response to describe in more detail the use of " raceway", " wireway", etc. for systems; provide clarifi-cation.
b)
Item 3 - Provide test write-up that identif,ies separation of relay contacts.
j i
031.49 - a) 7.2.1.1.4.2 - change " sensor" to " trip relay".
031.50-a)
Delete " diversity" discussions of 7.2.1.1.4.4.3, 7.2.1.1.4.4.4, 7.2.1.1.4.4.5.
031.51 -~a) 7.2.1.1.4.3, 7.2.1.1.4.4.5 - revise to clarify that channels are redundant and' operating bypasses are " independent".
Response must also be revised.
b)
Pg. 7.2-13 "The RPS reset switch..."; change to " switches for each channel..." - same on 7.2-18.
All but made switch should be plural.
J Pg. 3.1--
Change this page to indicate "4 manual scram controls".
23
'031.54 - a)
Respond to items 1 through 6 (to be coordinated in Tech Specs).
b)
.Briefly describe methodology used to arrive at setpoints.
Note that specific'setpoints will be provided in Tech Specs.
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Provide in FSAR Chapter'7 for all safety related instrumenta-tion: operating range, maximum allowable setpoints for the instrumentation.
-d)L Revise Figures 7.2-2, 7.2-5, and 7.2-6.
e)
Clarify whether scram is initiated by 3rd MSIV closure (Fig.17.2-2).
031.59 - a)
Pg. 7.3 first paragraph - verify interlock for manual initiation of containment spray and/or correct the appropri-ate elementary.
4 031.37 -
Item 1:
a)
Provide explanation of how we measure the time.
Provide normal procedure for testing.
031.38 - a)
Provide pick-up and drop-out voltage values and whether ESF instrumentation and controls are qualified over that range.
031.52 Add reference to rod pattern control in response for control of local damage.
031.57 GE will provide a copy of NED0-21617A (12/78) to SRL.
i 031.66 Item 2 Is NSLA adequate? State so-and cite any precedent in response.
031.78 - a)
Section 7.2/7.6 - Revise the information concerning the removal of shorting links from S. R. M. during refueling.
4 b)
Clarify monitoring during refueling.
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