ML20154R898
| ML20154R898 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 06/01/1988 |
| From: | Bailey J GEORGIA POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 1527V, GN-1458, NUDOCS 8806080246 | |
| Download: ML20154R898 (7) | |
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Georgia Power Company Route 2, Box 299A Waynesboro. Georg's 30830 Telephone 404 554 9961 404 724 8114 Southern Company Services. Inc.
Post Ottice Box 2625 Birmingham Alabama 35202 Teiepnone 20s 87asou p
June 1, 1988 U. S. Nuclear Regulatory Commission File: X7N16 ATTN: Document Control Desk Log:
GN-1458 Washington, D. C.
20555 V0GTLE ELECTRIC GENERATING PLANT - UNIT 2 NRC DOCKET NUMBER 50-425 CONSTRUCTION PERMIT NUMBER CPPR-109 TECHNICAL SPECIFICATIONS Gentlemen:
Attached for your staffs information is a meeting summary documenting the results of the April 27 and 28 meeting at the Vogtle Electric Generating Plant Site, concerning the VEGP Unit 1 and 2 Technical Specifications.
Sincerely, i
J. A. Bailey Project Licensing Manager JAB /HWM/1g Attachment xc: NRC Regional Administrator NRC Resident Inspector P. D. Rice L. T. Gucwa R. A. Thomas B. N. Churchill, Esquire J. B. Hopkins (2)
G. Bockhold, Jr.
R. J. Goddard, Esquire R. W. McManus Vogtle Project File 1527V
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8806080246 880601 I
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SUMMARY
OF MEETING WITH NRC ON COMBINED UNITS 1 AND 2 TECH SPECS APRIL 27-28, 1988 GROUND RULES We discussed the development of the combined Unit 1 and 2 Tech Specs.
It was proposed that the combined Tech Spec draft should consist of the current Unit i requirements with the necessary changes to account for the operation of Unit 2.
A request to change the Unit i license to incorporate the combined Tech specs will need to be submitted to the NRC. The current Unit 1 Tech Specs will be amended prior to the issuance of the Unit 2 license.
Such.
amendments will usually be applicable to Unit 2 as well as Unit 1.
It was suggested that future Unit 1 Tech Spec change requests clearly identify whether or not they are intended to be applicable to Unit 1 only or to both units.
The NRC explained that it was not their intent to re-review the Unit 1 Tech Specs but they may request explanation of some of the original Unit 1 Tech Specs.
The NRC indicated that the proof and review copy could be issued in about 2 months and that the final draft should be finished by mid October.
SPECIFICATIONS 6.4.1.6.e and 6.7.1.1 The Unit 2 draft Technical Specifications transmitted by the NRC's April 1, 1988 letter contained a proposed change to Section 6.4.2.2 which added a requirement for the SRB to review proposed FSAR changes to Chapter 16.
The j
process for preparation and review of FSAR changes was discussed. GPC i
explained how the commitments in Chapter 16 are controlled by procedures and proposed elimination of the NRC's proposed wording.
The NRC expressed their concern that the Tech Specs did not provide specific assurarce, that changes to those items that were removed from Tech Specs and placed in Section 16.3 of the FSAR would be reviewed prior to implementation.
It was noted that such review is currently being performed by the PRB and that the NRC request was applicable to Unit 1 as well as Unit 2.
GPC agreed to propose a revision to Specification 6.4.1.6.e that indicates the PRB review, by adding the following phrase, "including proposed changes to FSAR Chapter 16.3.
It was noted by GPC that the Technical Specifications Improvement Program implementation referred to in Specifications 6.7.1.1, is described in Chapter 16.3 of the FSAR. The NRC requested that this also be clarified by adding "FSAR Chapter 16.3" at the end of Specification 6.7.1.1.
j
CONTAINMENT STRUCTURAL INTEGRITY We discussed the application of Reg. Guide 1.35 Rev. 2 to our containment design and explained that the ability to detension tendons existed only on Unit 1.
The method of determining whether or not voids existed in the filler grease was raised by the NRC. The NRC requested further explanation of how we implement surveillance requirement 4.6.1.6.1.1.e.1 which requires verification of less than 5% voids in the filler grease.
It was-agreed to discuss this item at a later date by telephone.
It should be noted that this is a question for Unit i Technical Specifications.
POST ACCIDENT MONITORING The NRC requested that 3 instruments be added to Table 3.3-8.
They are position indication for PORV, PORV block valves and pressurizer safety valves.
It was noted that this table was intended to include only Reg.
Guide 1.97 Category 1 instruments and that the Category 2 and 3 instruments are covered by Specification 6.7.4.e.
No agreement was reached concerning this request.
It will be discussed again in a telephone conference to be arranged at a later date.
INSTRUMENT RESPONSE TIMES The NRC questioned the lack of ESFAS and RPS instrument response times in the Tech Specs.
It was explained that these items have been incorporated into the FSAR. Reference was made to the NRC Summary of the May 27-30, 1986 meeting, and the copy of the letter regarding the Seabrook Plant that th; NRC provided during that meeting was discussed. The NRC noted that re-inclusion of RPS and ESFAS response time was under discussion in the MERITS program.
This item is also equally applicable to the current Unit 1 Tech Specs. The question will 1, dropped but, the NRC stated that it may be raised at a later date for both u its through KERITS.
QUALIFICATION OF STA The footnote on page 6-5 that allows the STA position to be filled by a suitably qualified SRO or Operations Supervisor who is on shif t, was discussed. The NRC was concerned that the phrase (referring to the qualifications) "as required by NRC" was unspecific since potentially conflicting drafts of NRC requirements existed in public documents.
It was agreed that GPC would amend the Unit 1 (and thus Unit 2) Tech Specs to make it clear that the requirements are "as stated in the Policy Statement on Engineering Expertise on Shift, dated October 28, 1985."
ADDITIONS OF SPECIFICATION 3.0.5 The NRC proposed that a new section, 3.0.5, be added to explain how the combined Unit 1 and 2 Tech specs are applied.
This section would replace our proposed footnote that was intended to explain how the combined Unit 1 and 2 tech specs are applied to each unit and how common systems are addressed. A copy of the wording from the Catawba Plant Tech Specs was proposed by NRC.
GPC will review this and discuss it further with the NRC via telephone.
PRESSURE / TEMPERATURE LIMITS It was explained that Unit 2 Reactor Coolant System pressure temperature limits for Specification 3/4.4.9 were being prepared and would be provided by the end of August.
CONTROL ROOM VENTILATION A change to the Unit 1 Tech Specs will be submitted to allow removal of some of the panels in the temporary control room wall and an increase in the outside air flow rate to accommodate the larger volume. A more complicated Tech Spec change, that takes advantage of the four 100% capacity ventilation units will be submitted later, for Unit 1, to become effective when Unit 2 is licensed.
EDITORIAL CHANGES A number of editorial changes that do not affect the requirements were noted.
It was agreed that these would be submitted in a Unit 1 Tech Spec change.
PIPING PENETRATION AREA VENTILATION FLOW RATE The flow rate for Specifications 3/4 7.7 will be provided some time this fall, af ter its determination in the pre-op testing program.
SNUBBER TESTING The NRC will not agree with the requested change to the snubber testing during the first cycle without additional justification.
AREA TEMPERATURE MONITORING The Unit 2 rooms and their respective maximum normal and abnormal temperatures, that are subject to this specification, are to be provided for Table 3.7-3 by August.
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i ACTION ITEMS / COMMITMENTS 1.
A teleconference is to be organized to discuss the following items with NRC.
A.
Implementation of 4.6.1.6.1.1.c regarding verification'of 5% filler grease voids in containment tendons.
B.
Discussion of the reasons that we should not add PORV, PORV block i
valve and safety valve position indications to Table 3.3-8.
C.
Discuss the NRC proposed Section 3.0.5 that describes how combined Unit 1 and 2 Tech Specs are applied.
2.
Submit Tech Spec changes on Unit 1.
A.
Revise 6.4.1.6.e and 6.7.1.1 to clearly refer to FSAR _ Section 16.3.
B.
Clarify the footnote on page 6-5 to refer to "as stated in Policy Statement on Engineering Expertise on Shift" dated October 28, 1985.
C.
Provide a revision to incorporate editorial changes that do not change Unit i requirements.
3.
Unit 2 related Tech Spec changes or additional information.
A.
CONTROL ROOM HVAC Changes associated with combined control room operation are to be presented in support of the Unit 1 first refueling outage. These change will be incorporated into the Unit 1 & 2 draf t af ter they are finalized and submitted on Unit 1.
Specifications affected are:
3/4.7.6 pg. 3/4 7-14, 3/4 7-15, 3/4 7-16.
B.
APPENDIX "G" LIMITS Changes associated with the Reactor Pressure Vessel pressure /
temperature limits are expected that will account for differences in copper content and methodology for prediction of NDT shift. This affects power operated relief valve setpoints and heat up and cool down curves. GPC must decide whether or not it is desirable to have one set of enveloping requirements for both units.
Specifications affected are: 3/4.4.9 Figures 3.4-3 and 3.4-4, and bases Section B3/4.4.9 pages 3/4.4-30, 3/4 4-31, 3/4/4-32, 3/4 4-35, B3/4 4-7 through B3/4 4-11.
i
C.
VERITRAK l
l We proposed a temporary veritrak level instrument setpoint adjustment to account for environmental effects until the veritrak uncertainty issue is resolved.
It now appears that the issue will be resolved for both units. A change should be made on Unit 1 and Unit 2.
Specifications affected:
pg. 2-5 Table 2.2-1 and pg. 3/4 3-35 Table 3.3-3.
D.
CL2 SETPOINT
- The change in C12 setpoint from 2 ppm to 5 ppm is contingent on the approval of the Unit 1 submittal.
Consideration is being given to removal of the entire specification, and replacing it with a commitment to restrict C12 on site.
Specifications affected:
3.3.3.7 pg. 3/4 3-63.
E.
CONTROL BUILDING SUMP RADIATION MONITOR
- The proposed change for removal of the control building sump effluent radiation detector is contingent on its approval for Unit 1.
After the approval is received the modification will be made on Unit 2 and the change will be added to the Units 1 and 2 Draft Technical Specifications.
Specifications affected: Tables 4.3-5 and 3.3-9 pages 3/4 3-66 and 3/4 3-68.
F.
NaOH FLOW TEST RATE The Unit 2 specific values for the eductor suction flow test requirements cannot be provided until af ter Pre-op testing.
This is due in late fall of 1988.
Specificarion affected 4.6.2.2.d pg. 3/4 6-14.
G.
AFW PUMP TEST FLOW RATE
- A revision to the flow rate for the AFW motor driven pump test has been proposed for Unit 1.
It has already been included in the Units 1 and 2 draft as applicable to both units.
Affected specification 4.7.1.2.1.a.1 pg. 3/4 7-4.
H.
PENETRATION SYSTEM VENTILATION FLOW The Unit 2 specific Piping Penetration Area Filtration and Exhaust System flow rates for 4.7.7.b, d, e & f need to be provided af ter system balancing. The numbers are due in late fall 1988.
Specifications affected:
4.7.7.b, d, e, f, pg. 3/4 7-17 and pg. 3/4 7-18.
I.
AREA TEMPERATURE Table 3.7-3 should be revised to show Unit 2 rooms that are subject to the Area Temperature Monitoring Specification. The changes are expected by the end of August.
Specification affected: Table 3.7-3 pg. 3/4 7-28.
These represent requests for changes to the Unit 1 Tech Specs that we have incorporated into the draft Unit 1 aad 2 Tech Specs in anticipation of their approval by the NRC for Unit 1.
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