ML20024H350
| ML20024H350 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 05/21/1991 |
| From: | Kintner L Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9106030073 | |
| Download: ML20024H350 (14) | |
Text
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May 21, 1991 Docekt No. 50-416 LICENSEE:
Entergy Operations, Inc.
FAClllTY:
Grond Gulf Hutleer f acility, Unit 1
SUBJECT:
SUMMARY
OF AFRll 16, 1991 MEETING REGARDING LICENSING ACTIVITIES The NRC stof f inet with the licensee in its Rockville Offices to discuss proposed licensing octions, the status of open licensing octions and two recent GGNS Technical Specification Position Statertents. is a list of participonts. is en ogendo prepared by the licensee. is a list of line item technical specificetion improvements prepared by the licensee showing the status of each item. is e list of draf t questions on stotion blockout prepored by the stoff for discussion.
Comments were made on ogenda items as follows.
11.A.1 For the fifth refueling outage (April 1992) the licensee plans to reploce the triangulor shaped refueling mast with a less flexible circular shaped mast to focilitate fuel loading.
The new mast is heavier than the present mast so that limits in Technical Specifications (TS) must be changed.
The licensee plans to retair the present limits in TS 3/4.9.6
" Refueling Equipment" for use with the old most end add new limits for use with the new mast.
If the-new mest does not function properly, it could be replaced with the old most without requiring on emergency TS chenge.
The licensee is considering whether TS 3/4.9.7 " Crane Travel-Spent fuel and Upper contoinment fuel Storoge Pools" should 4150 be changed.
Presently, lodds in excess of 1140 pounds are prohibited from travel over spent fuel in the spent fuel pool or the upper containment fuel storage pool.
The new most plus fuel assen.bly weighs 1400 pounds. The licensee plans o sui;mittal by June 1,1991.
II.A.2 The licensee will request a schedule deferrol of the third integrated T E ate test (ILRT) until.the sixth refueling outage (RF0 6) which will begin in October 1993.
The second ILRT was run in RF0 3 (April 1989).
Since TS require o test intervel of 40 months plus or minus 10 months, o one time exception to this TS will be requestec.
Since Appendix J to 10 CFR 50 requires the thisd test to be run during the shutdown for the 10 year ISI inspection, a one tin.e exemption to Appendix J may also be needed. The TS change will be requested within 6 weeks and the exemption at least 6 months before it is needed.
II.A.3 A TS chonge will be requested to change the horizontal fuel transfer tube gote seal from on air seal to a water seal. The seol was designed as en air seel with a double o-ring ond means for pressurizing between the rings.
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_._____._____.__.m-2 However to test f or leakage with air, the water in the refueling canal must be drained, which increases the outage time.
The licensee proposed to demonstrate that there would be o 30-day water supply in the upper contairement pool. The pool has a weir wall which retains some water in the pool when the remainder is dumped to the suppression pool following o LOCA.
The staff noted that on equivalent water test for contoinment penetration seols hos not been previously accepted and requested that considerotion be given to modifications that would assure o valid air test without draining the water f rom the conal-for exemple o drain for water between the 0-rings.
II.A.4 A request for a TS change to allow use of elternate requirements for snubber visual inspections per Generic Letter 90-09 was submitted April 10, 1990.
It was requested thet the license amendment be issued by July 15, 1991, in order to schecule work for the contractor to be used in snubber surveillance tests.
11.B.1 A request to change the TS which limit the usage of the contoinment purge system during plant operation is being considered by the licensee.
In its SER doted December 26, 1990, the stoff had requested the licensee to change the limit from 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> to 400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br />, bosed on the dato provided by the licensee during the first two fuel cycles.
The licensee said it believed such a change would require a backfit analysis by the staff.
The staff does not believe backfit considerations are involved since the 1000 hour0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> limit was accepted as an interim limit at the time of licensing and the license was conditioned to require the determination of a permanent limit, based on plant operating data. The staff said the retention of a time limit seemed necessory since the use criteria proposed by the licensee were too general and would allow excessive use of the purge system.
The licensee said it would reconsider the criteria ond discuss them with the stoff by telephone.
II.B.2 The licensee said it planned to request d change to the surveillonce l
requirements for the containment and drywell hydrogen ignition system which l
require erection of scoffolding in the containment.
The request will be o part of the final analysis required by 10 CfR 50.44 The staff is considering
(
dn appeal by the Hydrogen Control Owners Group (HC0G) of the staff's generic l
SER on the Mark Ill conteinment hydrogen control provisions. The final analysis will be submitted within 6 months of the issuance of the staff's j
Supplement to the SER.
I I'. B. 3 Action g of TS 3.8.1.1 reporting A.C. electricol power sources T @ res testing of Division I and Division II diesel generators within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> if the Division III diesel generator is inoperable.
Action c ellows 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for testing the remaining two diesels if either Division I or Division 11 diesel generator is inoperable.
The licensee will request o change to l
Action 9 to make the allowed time for testing to be consistent with Action c.
II.B.4 A license amencment will be proposed to muve TS Table 3.6.4-1 to the Updated Finol Sofety Analysis Report (UFSAR) in order to facilitate chenges to required response times necessitated by testing of motor-operated volves per Generic Letter 89-10. The staff said generic guidance would be issued shortly and thot the submittal should be deft.rred until the guidance is issued.
II.B 5 TS changes to increase surveillance intervols of instrumentation will E sE mitted shortly.
The GE Topical reports supporting these changes have been approved by the stoff (See Enclosure 3).
II.B.6 Transfer of the rodiological effluent TS to the UFSAR per Generic Letter 89-01 will be requested shortly.
The TS would be transferrtd without chenge.
111.B Enclosure 4 gives stof f's draf t questions on the licensee's April 14, T975 response to 10 CFR 63 " Loss of all Alternating Current Power" (Station Blackout Rule) which were discussed to provide bockground information and clorification to the licensee's licensing personnel. The draft questions will be further discussed in a telephone conference cell between the stoft's technical reviewers and the licensee's engineering personnel May 22, 1991.
After this conference coli, o letter requesting odditional information will be issued with final questions.
Ill.G The stoff's October 1, 1990 SER of the licensee's response to Generic
[etter 88-01 recommends certain TS which were recommended in the Generic Letter.
In its Dececber 7, 1990 response, the licensee provided justification for not making changes to the TS.
Several other licensee's provided similar reosons for not making the TS changes recommended in GL 88-01.
The stoff is preparing a Supplement to the Generic Letter to change and clarify some of the TS recommendations based on information obtained in the review of responses to dote. Estimated issuance date is in June 1991.
IV.A The staff discussed its review of the GGNS Technical Specification N iition Statement (TSPS) No. 131. This TSPS provides an interpretation of TS 3.3.2 and TS 3.6.4 regarding Actions to be taken in Operational Conditions 4 or 5 with one of the two isolation valves in the common suction line from the reactor to the residuol heat removol system being inoperable and on inoperable trip system for one of the volves. The interpretation would allow one volve to be inoperoble and one of the two trip systems for the other valve to be inoperable for 14 days.
The TS is ambiguous since it states "one trip pidcing,ond/or isolotion valve moy be inoperable for up to 14 days without system the trip system in the tripped condition".
However, the safety evaluation for this requirement states thot one valve and its ossociated trip system must be operoble.
The TSPS interpretation appears to be inconsistent with the staff's interpretation in the safety evoluotion.
The staff will complete its review to determine if a TS change is required. The TSPS concludes a TS change is not required.
IV.B The stof f noted that TSPS No.132 concluded that o TS change is not required even though the current,TS value of the minimum air pressure in the diesel generator air start receivers was identified in e GGNS Quality Deficiency Report (ODR) as non-conservative with respect to the emergency stort lock-out setpoint. The TS value of minimum pressure is 160 psi and the TSPS value is 195 psi.
The emergency start lock out setpoint is 160 psi.
Finel resolution of the Quality Deficiency Repor t is pending. The staff will followup the resolution of this ODR and disposition of the TSPS.
l The staff provided tar 9et dates for issuonce of pending licensing actions as follows:
Reanalysis of the reactor water cleanup system line break ossuming isolation by high flow instead of high temperature - December 14, 1991.
Cancellation of the Unit 2 construction permit - July 31, 1991.
Change fire protection license condition and tronsfer TS to the UFSAR per Generic Letter 88 Mey 30, 1993 (Subsequently changed to June 30, 1991)
Chenge TS concerning minimum volume of fuel oil required for diesel generators - June 30, 1991 based on response to RAI by April 30, 1991.
Chenge TS concerning chenges to 125 VDC battery lood profiles -
August 16, 1991 based on receipt of response to RAI by 3/31/91.
Change TS for standby liquid control system - Moy 31, 1991.
Groundwater level control and monitoring - July 31, 1992 based on receipt of a final report by April 30, 1992.
A request for proposed TS for o dewatering system if necessory to control water level below the design basis level is scheduled for issuance by June 30, 1991.
In response to licensee questions the staff said it does not consider this a bockfit because the stoff deferred any position on this issue at the time of licensing Unit I until construction of Unit 2 was completed and the post-construction water level without operation of dewatering wells could be determined.
Transfer of the schedule for removal of the reactor pressure vessel surveillonce specimens from the TS to the UFSAR per Generic Letter 91-01
- July 23,1991 based on receipt of the response to RAI by May 23, 1991.
TS change to remeve the 3.25 limit on three consecutive surveillonce intervals - June 30, 1991 Changes to TS administrotive controls of reflect o change to the title of the GGNS Generol Manager - May 30, 1991.
Revision of 15 reporting requirements to nioke them " pursuant to 10 CFR 50.4" - July 31,1991 based on the assumption changes will not be required. The application is ddted April 11, 1991 and stoff had not begun its review at the time of the meeting.
1
( ! ekti Lester L. Kintner, Sr. Project Manager Project Directordte IV-1 Division of Reottor Projects Ill, IV, and V
Enclosures:
As 50ted Office of Nuclear Reactor Regulation cc:
See next je
l Mr. W. T. Cottle 4
Entergy Operations, Inc.
Grand Gulf Nuclear Station cC*
Mr. Fred W. Titus Mr. C. R. Hutchinson Vice President, Engineering GGNS General Manager Entergy Operations Inc.
Entergy Operations, Inc.
P. O. Box 31995 P. O. Box 756 Jockson, Mississippi 39286-1995 Port Gibson, Mississippi 39150 Robert B. McGehee, Esquire The Honorable William J. Guste, Jr.
Wise, Corter, Chilo & Cardway Attorney General P. O. Box 651 Deportment of Justice Jeckson, Mississippi 39205 State of Louisiana P. O. Box 94005 Baton Rouge, Louisiand 70804-9005 Nicholas S. Reynolds, Esquire Winston & Strawn Alton B. Cobb, M.D.
1400 L Street, N.W. - 12th floor State Health Officer Washington, D.C.
20005-3502 State Board of Health P. O. Box 1700 Jackson, Mississippi 39205 Mr. Jim T. LeGros Manager of Quality Assurance Office of the Governor Entergy Oper ations, Inc.
State of Mississippi P. O. Box 31995 Jackson, Mississippi 39201 Jackson, Mississippi 39286-1995 President, Mr. Jack McMillon, Director Claibcrne County Board of Supervisors Division of Solid Weste Management fort Gibson, Mississippi 39150 Mississippi Department of Natural Resources Regional Administretor, Region 11 P. O. Box 10385 U.S. Nuclear Regulatory Commission Jackson, Mississippi 39209 101 Marietta St., Suite 2900 Atlanta, Georgie 30323 Mr. Michael J. Meisner Director, Nuclear Licensing Mike Morre, Attorney General Entergy Operations, Inc.
Frank Spencer, Asst. Attorney General P. O. Box 756 State of Mississippi Port Gibson, Mississippi 39150 Post Office Box 22947 Jackson, Mississippi 39225 Mr. C. B. Hogg, Project Manager Bechtel Power Corporation Mr. Gerdid W. Muench
=
P. O. Box 2166 Vice President, Operations Support Houston, Texas 77252-2166 Entergy Operations, Inc.
P. O. Box 31995 Mr. Johnny Mathis Jackson, Mississippi 39286-1995 Senior Pesident Inspector U.S. Nucleor Reguletory Commission Mr. Donald C. Hintz, Executive Vice Route 2, Box 399 President & Chief Operating Officer Port Gibson, Mississippi 39150 Entergy Operations, Inc.
P. O. Box 31995 Jackson, Mississippi 39286-1995 9
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ATTENDANCE 4/10/91 MEETING ENTERGY OPERATIONS, INC - NRC Nome Affiliation T Quoy*
NRC, Dir., PDIV-1 P. O'Connor NRC, PDIV-1 R. Twigg*
NRC, PDIV-1 A. Toalston*
NRC, SELD J. Kudrick*
NRC, SPLB J. Fowler Entergy, GGNS
- Port Time l
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AGENDA GGNS/NRC LICENSING ACTION STATUS MEETING Date:
APRIL 16, 1991 Time:
8:30 AM Place:
CONFERENCE ROOM 10/B/13 NRC WHITE FLINT OFFICES ROCKVILLE, MARYLAND I.
INTRODUCTION AND PURPOSE OF THE MEETING II.
DISCUSSION OF PROPOSED LICENSING ACTIONS A.
Major Licensing Actions needed for RF05:
1.
Modifications to the Refueling Platform Main Hoist 2.
Deferral of the third ILRT until RF06 3.
Relief from leak rate testing of the Horizontal Fuel Transfer Canal Gate 4.
Generic Letter 90-09; Alternate Requirements for Snubber Visual Inspections 5.
Reg. Guide 1.97; Neutron Monitoring Deferral B.
Other Proposed Actions:
1.
Tech Specs for Restricting use of the Containment Purge System 2.
Iccessibility of Hydrogen Ignitors; Revision / Relocation of TS Ta,ble 3.
Division III Diesel Generator Action Statement 3.8.1.1.g 4.
Relocation of the Containment Is.olation Valve Table from TS to UFSAR 5.
Extension of Surveillance Intervals and Allowed Out-of-Service Times for ESF Instrumentation (Common, Rod Block, ECCS, and Isolation Actuation Instrumentation )
6.
GL 89-01; Relocation of RETS to ODCM/PCP
III. STATUS OF OPEN LICENSING ACTIONS A.
Revisions to RWCU Leakage Analysis B.
Discussion of Draft SBO Questions C.
Unit 2 Construction Permit Cancellation Schedule D.
Deletion of Fire Protection TSs E.
Diesel Generator Fuel Oil Tank Capacities F.
Deletion of the 125 VDC Battery Load Profiles G.
GL 88-01; IGSCC Related TS Changes H.
Standby Liquid Control Tech Specs I.
De-watering Wells J.
GL 91-01; Removal of the Schedule for Withdrawal of Reactor Specimens from TS K.
GL 89-14; Removal of the 3.25 Limit on Extending Surveillance intervals L.
Revision to the Title of the GGNS General Manager M.
Revision to TS Chapter 6 Reporting Requirements to Remove Inconsistencies with 10CFR50.4 IV.
TS POSITION STATEMENTS A.
TSPS 131, Operability Requirements for F008 and F009 RHR Isolation Valves B.
TSPS 132, DG Air Sturt Receiver Pressure Set-point m
REFERENCE #
SUBJECT STATUS GL 86-10 Implementation of Fire Protection Submitted 5/19/87 Requirements AECM-87/0046 GL 87-09 Sections 3.0 and 4.0 of the Standard Approved Amendment 69 Technical Specifications (STS) on the Applicability of Limiting Conditions for Operation and Surveillance Requirements GL 88-06 Removal of Organization Charts from Approved Amendment 45 Technical Specification Administrative Control Requirements GL 88-12 Removal of Fire Protection Submitted 8/22/90 Requirements from lechnical AECM-90/0134 Specifications GL 88-16 Removal nf Cycle-Specific Parameter Submittal Pending Limits from Technical Specifications (1992) Target GL 89-01 Implementation of Programmatic Submittal Pending Controls for RETS in the (05/91) Target Administrative Controls Section of the TS and the Relocation of Procedural Details of RETS to the ODCM or to the PCP GL 89-14 Line-Item Improvements in Technical Sebmitted 3/15/91 Specifications - Removal of the 3.25 GNRO-91/00039 Limit on Extending Surveillance Intervals GL 90-02 Alternative Requirements for Fuel No submittal planned Assemblies in the Design Features Section of Technical Specifications GL 90-09 Alternative Requirements for Snubber Submittal Pending Visual Inspections (4/91) Target GL 91-01 Removal of the Schedule for the Submitted 3/15/91 Withdrawal of Reactor Vessel GNRO-91/00047 Materials Specimens from TS NEDC-30851P-A RPS Instrumentation A0Ts/STIs Approved Amendment 67 NEDC-30851P-A, Isolation Instrumentation Common Submittal Pending Supp. 1 to RPS/ECCS A0Ts/STIs (4/91) Target NEDC-30851P-A, Control Rod Block Instrumentation STIs Submittal Pending Supp. 2 (4/91) Target M9104091/SNLICFLR - 1
m.
REFERENCE #
SUBJECT STATUS
.NEDC-30936P-A ECCS Instrumentation A0Ts/STIs Submittal Pending (4/91) Target NEDC-31677P-A 1solrition Actuation Instrumentation Submittal Pending A0Ts/STIs
-(4/91) Target J
GENE-770-06-1 Selected TS Instrumentation A0Ts/STIs Submittal Pending (6/91) Target GENE-770-06-2 RCIC Instrumentation A0Ts/STIs Submittal Pending (6/91) Target i
4 4
I
.f M9104091/S:,'LICFLR - 2 4
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301 492 C2602* 10
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9-7a3 - 22i - n 27 Page 1 of 2 QUESTIONS OH GRAND GULF NUCLEAR STATION SBD SUBMITTAL' WITH EMPHAS!$ ON THE FOLLOWING AREAS 1)
AC Power Design Characteristic Group a)
The submittals indicate the extremely severe weather (ESW) group to be a *2" whereas the ESW grouping given in NUMARC B7 00 is "4."
The licensee stated in the submittal dated March 30, 1990, that the NUMARC 87 00 value is in error and that this error was confirmed based upon discussions with the NRC staff. Justify the discrepancy between the estimated ESW assignment in the submittals and that given in NUMARC 87-00 by providing documentation of the NRC staff's acknowledgement of the error, b)
Briefly describe the "I" classification.
2)
Condensate Inventory a)
Provide a breakdown of the contributing elements used in the calculation for the condensate required (i.e., decay-heat removal, cool down, leakage, etc.).
b)
Whatsystem,HPCIorRCIC,willbeusedduringanSB0 event?
(The submittal is unclear.)
3)
Battery Capacity a)
The submittals indicate that the Division-I batteries are inadequate to cope with a four hour $80 event, making load stripping necessary.
Explain what will be stripped and when it will be stripped.
- and supporting documentation March 21, 1991
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- 3 31-91 11:26cN 3 70344201964 301 492 02603011
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Page 2 of 2 b)
. Provide the battery load profile and the assumptions made battery capacity calculations.
c)
A sentence on page 7 of the March 30, 1990 submittal is unclear.
"A requirement will be added to the Loss of AC Power ONEp to trip t RCIC gland seal compressor if both Division I and II ESF Bu lost."
What is meant by the loss of both Division I and 11 ESF busses (i.e., loss of EDC's, loss of batteries, etc.).
4)
Effects of Loss of HVAC (detailed explanation may be needed):
l a)
How were the areas of concern chosen?
i b)
What methodology was used to calculate the room temperatures?
i 1
c)
What were the assumed initial temperatures?
d)
What is the drywell temperature assuming a 61.gpm Icak rate?
b e)
Were calculations performed pe5 the control room and switchg room?
What will the temperature be in the main steam tunnel?
~
What equipment will need to be operable in the main steam tunnel?
5)
Containment Isolation a)
Provide a list of valves that require manual action to ensure tneir closure under SB0 conditions.
b)
What valves were excluded by the additional two criteria provided i the submittal dated March 30, 19907 4
March 21, 1991 l
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The stof f provided torget dotes f or issuance of pending licensing octions os follows:
Reanelysis of the reactor woter cleanup system line break ossuming isolation by high flow instead of high temperature - December 14, 1991.
Cancellotion of the Unit 2 construction permit - July 31, 1991.
Chonge fire protection license condition and transfer TS to the UFSAR per Generic Letter 68 May 30,1991 (Subsequently chonged tu June 30, 1991)
Change TS concerning minimum volume of fuel oil required for diesel generators - June 30, 1991 based on response to RAI by April 30, 1991.
Change TS concerning changes to 125 VDC battery load profiles -
August 16, 1991 bosed on receipt of response to RAI by 3/31/91.
Change TS f or standby liquid control system - May 31, 1991.
Groundwater level control and monitoring - July 31, 1992 bosed on receipt of a final report by April 30, 1992.
A request f or proposed TS for a dewatering system if necessory to control woter level below the design basis level is scheduled for issuance by June 30, 1991.
In response to licensee questions the staff said it does not consider this a backfit because the staff deferred any position on this issue at the time of licensing Unit I until construction of Unit 2 was completed and the post-construction water level without operotion of dewatering wells could be determined.
Transfer of the schedule for removal of the reoctor pressure vessel surveillance specimens from the TS to the UFSAR per Generic Letter 91-01
_ July 23, 1991 based on receipt of the response to RAI by May 23, 1991.
TS change to remove the 3.25 limit on three consecutive surveillance intervals - June 30, 1991 Changes to TS edministrative controls of reflect a change to the title of the GGNS Generel Manager - May 30, 1991.
Revision of TS reporting requirements to moke them " pursuant to 10 CFR 50.4" - July 31, 1991 based on the assumption changes will not be required. The applicotion is dated April 11, 1991 and stoff hed not begun its review ot the time of the meeting. On..ginal si Lester L. Kintner,.Sr.gan Ay Project Moneger Project Directordte IV-1
Enclosures:
As stated Qivision of Reactor Projects III, IV, and V cc: See next page Office of Nuclear Reoctor Reguldtion 1
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NAME:L[nt.er
- TQuey DATE.$//P/91 9/1\\/91 OFFICI AL p CORD :CFY l
Document Name: GG MEETING
SUMMARY
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