ML20154E651

Summary of 880815 Meeting W/Util Re Potential Changes to Tech Specs.Other Actions Discussed Includes,Status of Completion of Conditions in Operating License & Actions Taken Re Problems Identified in Info Notices

ML20154E651
Person / Time
Site:	Grand Gulf
Issue date:	09/14/1988
From:	Kintner L Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8809190086
Download: ML20154E651 (7)

Text

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. l Docket No. 50-416 September 14, 1988 DISTRIBUTION See next page LICENSEE: System Energy Resources, Inc.

FACILITY: Grand Gulf Nucelar Station, Unit 1 i

SUMMARY

OF AUGUST 15, 1988 MEETING REGARDING POTENTIAL CHANGES TO THE TECHNICAL SPECIFICAT10h5 The purpose of the meeting was to discuss potential changes to the Technical

, Specifications (TS). Other licensing actions were also discussed including the l status of completion of conditions in the operating license and actions taken regarding problems identified in information notices and commitments mode in

, previous licensing actions. Enclosure 1 is a list of participants. Enclosure 2 is an agenda proposed by the licensee.  !

j The following comments were made regarding the agenda items in Enclosure 2.

_l.A.2 Thepresentspecification(4.9.6.1.b.1)requiresthedowntravel cutoff for the refueling rain hoist to be 3.5 i 0.5 inches below the top of fuel assembly handles in the core. With the lengthened fuel assemblies due to irradiation, the downtravel cutoff point say be too high to grapple control rod guide handles. Difficulty was experienced i in this regard during the second refueling; and it is expected to be more difficult, if not impossible, to meet the TS during the next refueling outage. The proposed specification would :be for downtravel

, cutoff to be greater than or equal to onu inch above the reactor vessel top guide, a fixed referenced point. The basis for the l

specificetion limiting downtravel is to prevent the grapple from t engaging the top guidc instead of a fuel assembly handle. The '

licensee believes this change would only be applicable to BWR-6's. ,

l.A.3 The addition of a footnote taking exception to local leak rate tests  !

(LLRTs) for containment isolation valves in test, vent, and drain l lines in TS Table 3.6.4-1 would reduce the potential for LLRTs to be '

on the outage critical path. Administrative Controls would be used to assure that valves are left in the closed position after maintenance. The BWR Owners Group is recommending this change.  !

1.A.4 The licensee commented that some modes of spent fuel cooling during i outages may be affected by having the spent fuel pool gate in place. l However, having this gate and the upper containment pool gate in place t would allow work to be done on the horizontal fuel transfer mechanism, if needed. The licensee will consider effects on spent fuel cooling i in its safety analysis of the proposed TS change.

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2 I.A.5 The licensee raised the question again whether the rodel Bases for TS 4.0.3 were correct in Generic Letter 87-09. In the June 14 and 15, 1988 meeting (Summary dated 8/8/88), the licensee had questioned whether a missed surveillance test must be reported as a TS violation. Staff in the Technical Specifications Branch reaffirmed that a missed surveillance test should be reported as a TS violation, whether or not the allowed outage tire of the action statement has been exceeded at the time of discovery of the missed surveillance test.

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Regard'ng the new alternate decay heat removal system to be installed in the third refueling outage, two new TS will be proposed. P.

Radiation monitnrs will be added to the plant service water (PSW) system because PSW will be used in the new heat exchanger. Thermal overload devices for the motors operating isolation valves in the new system will be added to TS. The licensee will perform a 10 CFR 50.59 review of the system to determine whether to submit the system design criteria to NRC for approval prior to installation. The staff requested that a description of the system and safety analysis be provided with the proposed TS r.hanges.

Ill.A The staff indicated that the licensee's 8/3/88 proposed implementation of the 10 CFR Part 55 rule was adequate and that the revised application for TS change would be renoticed.

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The licensee stated that a TS change would be submitted in August to remove unecessary organization position titles from TS Section i

6.0.

The staff requested that information be providea in the next meeting regarding the following:

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- Disposition of a July 6,1987 proposed TS change to delete the requirement for isolation valve instrumentation to be operable 1

during shutdown. The staff had indicated in previous meetings that the proposed cha g e is not acceptable.

- An update of J. G. Cesare's remo dated 10/22/86 which gives the status of completion of Operating License conditions.  :

- A description of procedures implernenting the use of MSA GMR-1 canisters, in its Exemption to 10 CFR Part 20 permitting their use, the staff  :

required procedures to be in place within a certain time.

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- A description of how assurance has been obtained that gaps in neutron l absorber material in hign density fuel racks are not a problem at Grand Gulf Nuclear Station, Unit 1 as they were at another f acility that nad

installed Joseph Oats fuel racks. (IN 87-43)

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Enclosure 1 PARTICIPANTS AT AUGUST 15, 1988 MEETING REGARDING TS CANGES J.G. Cesare SERI, Director of Licensing J. Fowler SERI, Licensing J.K. Fortenberry SERI Licensing L. Kintner NRC, Project Directorate, 11-1 R. Emch* NRC, Section Head TSB T. Dunning

• NRC Technical Specifications Branch l

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Enclosure 2 TECH SPEC MEETING August 15, 1988 I. RF03 LICENSING ACTIONS FOR DISCUSSION REFERENCE A. TECH SPEC CHANGES

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2. Refueling Platform Main Heist Down T.S. 4.9.6.1 b.1 ,

Travel Cutoff -

3. LLRT Requirements for Containment T.S. Table 3.6.4-1 Penetration Isolation Test, Vent &

Drain Valves

4. Upper Containment Pool Fuel Transfer T.S. 3.5.2/3.5.3 Canal Gate Footnote *

5. Generic Letter 87-09 B. OTHER RF03 LICENSING ITEMS

1. Exception to R.G. 1.108 to Allow Only R.G. 1.103 Section C One LOP /LOCA Test for 0/Gs I, II & III

2. Alternate Decay HLat Removal System II. NON OUTAGE TECH SPEC CHANGES A. DELETION OF T.S. CHAPTER 6 REFERENCES GL 83-06 TO ORGANIZATION POSITIONS B. COMBINED SRO/STA POSITION GL 86-04 C. RWCU DELTA-FLOW TIMER BYPASS J14MISCSS072801 - 1

4 I!!. OTHER ITEMS FOR STATUS REFERENCE, A. 10CFR55 RULE AECM-88/ 0146 8/3/88

8. DELETION OF FIRE ZONE OC506 FROM T.S. AECM-88/0114 Table 3.3.7.9-1 7/12/88 C. 0/G TEST SCHE 0VLE AECM-88/0049 (Amendment issued) 4/8/88

0. DELE 110N OF LPSP/HPSP OAILY FUNCTIONALS AECM-88/0105 6/21/88 E. SCRAM ACCUMULATOR ACTION STATEMENT AECM-S8/0071 4/22/88 F. DELETION OF ORGANIZATION CHARTS AECM-88/0106 i (Amendment issued) 6/3/S8 I G. RPS INSTRUMENTATION SURVEILLANCE INTERVALS / ACCM-88/0118

. ALLOWE0 OUT-OF-SERVICE TIMES 6/30/88 4

. H. DELETION OF THE SNUBBER TEST REJECT REGION AECM-88/0149 4

7/25/88 I I. SEPARATION OF THE 24 HR 0/G TEST FROM AECM-88/0150 THE LOP /LOCA TEST 7/26/S8

! J. WIDE RANGE NEUTRON MONITORING AECM-88/0110 7/1/88 l

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DISTRIBUTION FOR HEETihG SL'MMARY '0ATED: September 14, 1988 Facility: GRAWD GULF UNIT 1 Mckei311e.[4 NRC POR Local FOR PO!!-1 Reading E. Adensam P. Anderson Project Manager OGC E. Jordan (MNBB 3302)

8. Gris)es (9A2)

NRC Participants ACRS (10)

8. 'roskoski (17019) cc: Licensee / Applicant Service List h

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. Whether responses to Generic Letter 83 28 dated 3/30/88 and 10/16/87 should be applicable for Unit 2. as wcil as Unit 1, since all other l responses and SER's for GL 83 28 are for both units. j

- A description of how assurance has been obtained that  !

springs in main steam isolation valves are not broken, as they were in another facility using the same design valves (IN 86 81).

. A descriptien of plans for providing additional heat removal capability, or justifying present capability, for the high density Spent fuel pool when full capacity is authorized. Present TS limit the number of fuel l assemblies which can be stored in the spent fuel. A commitment was made '

to provide this analysis by the third refueling outage.  !

The next meeting was tentatively scheduled for the last week in August. The I agenda will include discussions of previously submitted applications on which I reviewers have questions.

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t Lester L. Kintner, Senior Project Htaager j Project Directorate II.1 ,

Division of Reactor Projects I/11 l cc: See next page l r

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