ML19332C398
| ML19332C398 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 11/15/1989 |
| From: | Kintner L Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| GL-83-28, GL-86-10, GL-87-09, GL-87-9, GL-88-12, GL-88-20, GL-89-09, GL-89-10, GL-89-9, NUDOCS 8911280074 | |
| Download: ML19332C398 (11) | |
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Io UNITED STATES g
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NUCLEAR REGULATORY COMMISSION 3.'
.t WASHINGTON, D. C. 20S55
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November 15, 1989
' Docket No.
50-416 LICENSEE: System Energy Resources,-Inc.
(SERI)
FACILITY: Grand Gulf Nuclear Station, Unit 1 (GGhS-1)
SUBJECT:
SUMMARY
OF SEPTEMBER 19, 1989 MEETING AND TRIP TO GGNS-1 t
The NRC staff niet with the licensee at the GGNS-1 Site to discuss future licensing activities. On September 20 and 21, 1989, the NRC Project Manager discussed selected activities with the SERI licensing and engineering staff,
. provides a list of participants in the meeting. Enclosure 2 is a copy of the agenca for the meeting.
The licensee provided adoitional information cn several activities as follows:
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Regarding followup on the loss of main condenser vacuum event and associated equipn:ent failures, General Electric Company is preparing a report on the failure of one control rod to fully insert.
o Regarding the requirement for secondary containment integrity when handling loaos over spent fuel, the licensee plans to put curves of load allowable height versus weight in procedures and change the Technical Specifications (TS) regarding secondary containment integrity to specify the impact energy above which integrity will be requireo. The licensee aavised that revised application would be submitted, o
The license amendment request for GGNS-1 1mproved TS is planned to be submitted in April 1990. A markup of the present GGNS-1 TS is schdcleo for January 1990. A task force of four disciplines and operations personrel is working on the improved TS, including 5-7 engineers from Nuclear Plant Engineering, core physics and licensing. A procedure and quality control are in place. Training and surveillance procedures to use the improved TS have not yet been included in detaileo planning. The submittal will identify the location in the updated FSAR where TS requirements have been placed anc will cescribe administrative controls, o
A new TS for engineered safety feature rocm coolers is planned. The TS would define allowed outage tines (A0Ts), if room coolers become
-inoperable, that are consistent with A0Ts for ecuipment in the rooms.
This would be a follow up to LER 86-29, which describes corrective actions for low flows in room coolers due to corrosion induced flow restrictions in pipes. A BWR Owners Group is discussing this subject with hRC the similar Technical Specification Branch.
Licensee is consicering(Letter odted situation at Clinton for guidance in preparing the TS.
August 21, 1989 from Murley).
o The licensee advised that in response to staff's request for information regarding prying action on base plates for pipe supports, they had b
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provided staff reviewers with 240 revised baseplate evaluations, using
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current methods. The staff confirmed that reviewers are considering those calculations.
Subsequent to the meeting, staff advised licensee that its report on pipe support calculations is due November 30, 1989.
o The licensee is planning to submit a proposed TS change to allow the use of water leakege tests rather than air. tests for feedwater isolation valves.- Water would be maintained in the feedwater line following an accident by its keep fill system.
Perry uses this methoa of containment isolation. Maintaining leakage within TS limits using air tests requires replacement of resilient seals every outage, o
The licensee will respond to GL 88-20 regarding an IPE by October 31, 1989. SERI is planning to use the same technology as that used in NUREG-1150. A tentative scheoule for getting an operational tool is 3 years.
o Regarding GL 89-10 on M0 VATS, licensee said because of the large number of safety related MOVs in the Mark III containment (300) the reconnended schedule in GL 89-10 for completing all design basis reviews, analyses,-
verifications, tests and inspections woulc significantly extend outage schedules. The licensee will propose an alternative schedule based on prioritization according to safety function, o
The licensee stated that its schedule to implement its new method of clarifyirg safety related equipment per Generic Letter 83-28 position 2.1.1 was changed from June 1989 to November 1989 (Item 15, Page 7 of licensee's June 17, 1988 letter).
o The li m re: :tci.6 diat it has revised its procedures for 10 CFR 50.59 reviews. The procedures have been reissued with NSAC - 125, the NUi4 ARC guideline document, enclosed. Training is according to INP0 guidelines.
A subcommittee of the SRC reviews 10 CFR 50.59 safety evaluations.
The staff notes that the' revised procedures do not specify qualifications for performing screening or safety evaluations and that screening does not determine whether a change affects nuclear safety.
Screening only determines whether the equipment or procedure changed is in the FSAR.
Previous staff reviews of procedures reconsnended these two changes to the procedures.
The staff provided information regaraing the following matters:
o Regarding the proposed TS change to the stendby liquid control system, the licensee questioned why TS 4.1.5.6.3 specifies determination of both the weight of sooium pentaborate and the concentration of boron in solution, since the weight is calculated from the concentration as determined by chemical analysis of a sample of solution.
Subsequent to the meeting, the staff advised the licensee that deletion of weight determination is acceptable.
o The proposed TS change allowing larger surveillance test internals for the reactor protection system is scheduled to be issued December 31, 1989.
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o Regarding the proposed TS change to delete local leak rate testing of small (1 inch diameter or less) test, vent and drain valves, the licensee stated that other utilities do not have such requirements in the TS.
Integrity is verified by inspection. Subsequent to the meeting, the staff advised the licensee that this matter is being considereo generically and will be resolved in the TS Improvement Program. Therefore, the proposed TS change will be rejected, o
The proposed TS change regarding PSRC and SPC composition and combining the STA and SR0 responsibilities under one person was scheduled to be issued. September 30, 1989. Licensee stated that a new TS proposal to delete the site director position and change the radiation protection manager ano. training supervisor positions wculd be filed shortly.
.o The staff said it would give the review of the revised application for a TS change per GL 87-09 a higher priority.
This amendment would change
- TS 3.0.4. to allow mode changes while in action statenents, provided administrative procedures-are in place to assure proper use of the change.
The staff said it expected such mode changes to have a written safety evaluation prior to the mode change.
The licensee said it planned to have the PSRC review such operations and document the evaluation in PSRC-minutes. Licensee will provide this information by letter to supplement its application.
o In response to the licensee's request for clarification of Generic Letter 69-09_ regarding ASME Section III component replacements, the staff commented on licensee's proposed clarification (Enclosure 3). Staff agrees with three of the four clarifications. However, the staff does not agree with licensee's proposed alternative to listing the GL 89-09 replacements in the FSAR.
o Subsequent to the meeting, the staff adviseo that the containment purge program review by Jack Kuorick would be ccmpleteo by January 31, 1990.
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o The staff said its review of the General Electric topical report regarding I
neutron flux monitoring to meet the requirements of Regulatory Guide 1.97 would be completed by December 31, 1989.
The licensee indicated its alternative of installing an encore detector by the fourth refueling requires a decision by January 1990, o
The staff requested that 10CFR 2.790 proprietary information included in L
applications be properly identified in the letter of transmittal ano that l
an affidavit requesting withholding be enclosed (per August 1, 1989 memo of John T Larkins to NRR Project Directors).
o The staff requested information regarding the licensees measures to control the spread of hot particles. The licensee described its procedure in the plant operations manual for controlling hot particle contamination (Procedure 08-8-02-21 Revision 1, oated March 10,1989).
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The staff questioned why the chemistry TS Surveillance Requirement 4.4.4.c does not limit outage of the continuous conductivity monitor L
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that SSER Supplement 6 acc00ted the deletion (Page 16-103). Also, from a practical view point, the aiternative of sampling every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is too i
burdensome to continue for long periods of time._ Subsequent to the j
meeting, the staff advised the licensee that it will not be necessary to
- make the TS like the Standard TS.
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'The staff discussed its review of the revised fire protection program.
The licensee said staff's conclusion that only two safety relief valves would be damaged by any one fire is not supported by its submittals.
Staff will arrange a meeting to discuss the fire protection program and the proposed license condition per Generic Letters 86-10 and 88-12.
Original Signed By:
L. L. Kintner, Senior Project Manager Project Directorate II-1 Division of Reactor Projects 1/II
Enclosures:
As Stated cc w/ enclosures See next page
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.NAME :PArde on LK1 er:d A e sam DATE 11/ J b /89 11/l5/89 114ji/89 0FFICIAL RECORD COPY
. Document flame: SYSTEM ENERGY RESOURCES INC.
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. System Energy Resources, Inc.
Grand Gulf tiuclear Station (GGNS) l 1
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Mr. T. H. Cloninger fir. C. R. Hutchinson Vice' President, huclear Engineering GGNS General Manager
& Support System Energy Resources, Inc. -
System Energy Resources, Inc.
P. O. Box 756 P. O. Box 31995 Port Gibson, Mississippi 39150
, Jackson, Mississippi 39286 Rcbert B. McGehee, Esquire The Honorable William J. Guste, Jr.
Wise, Carter, Child, and Attorney General J
Caraway Department of Justice P. O. Box 651 State of Louisiana
~ Jackson, Mississippi-39205 Baton Rouge, Louisiana 70804 Nicholas S. Reynolos. Esquire Office of the Governor Bishop, Cook, Purcell State of Mississippi and Reynolds Jackson, Mississippi 39201 l
1400 L Street, N.W. - 12th Flocr Washington, D.C.
20005-3502' Attorney General Gartin Builoing Mr. Ralph T. Lally Jackson, Mississippi 39205-Manager of Quality Assurance Entergy Services, Inc.
Mr. Jack licMillan, Director P. O. _ Box 31995 Division of Solio Waste Management Jackson, Mississippi 39286 Mississippi Department of Natural Resources P. O. Box 10385 Mr. John G., Cesare Jackson, Mississippi 39209 Director, touclear Licensing System Energy Resources, Inc.
Alton B. Cobb, M.D.
P. O. Box 469 State health Officer Port Gibson, Mississippi 39150 State Boarc of Health P. O. Box 1700 fir. C. B. Hogg, Project lianager Jackson, Mississippi 39205 Bechtel Pa er Corporation-P. O. Box 2166 President Houston, Texas 77252-2166 Claiborne County Board of Supervisors Port Gibson, Mississippi 39150 Mr. H. O. Christensen l
Senior Resident Inspector Regional Administrator, Region II U.S. Nuclear Regulatory Commission U. S. Nuclear Regulatory Comission Route 2, Box 399 101 Marietta Street Port Gibson, Mississippi 39150 Suite 2900 Atisr.ta. Georgia 30323 t
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j'i -. 4 DISTRIBUTION FOR MEETING
SUMMARY
DATED:~ November 15,1989 Facility: Grand Gulf h
Decket"'Pite=~
NRC PDR Local PDR T. Murley 12-G-18 J. Sniezek 12-G-18 E. Adensam=
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.P. Anderson 14-B-20 L. Kintner 14-B :
OGC 15-B-18
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L i-ENCLOSURE 1 Attendees September 19, 1989 Meeting NAME AFFILIATION i
George Zinke SERI-Licensing D. L. Pace SERI-NPE Steve Bennett SERI-NL John Fowler SERI-NL Yosi Balas Licensing M. L. Crawford SERI-NL F. W. Titus SERI-NPE J. G. Cesare SERI-NL H. O. Christensen NRC Senior Resident Inspector L. L. Kintner NRC Senior Project Manager f
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'NRC-SERI LICENSING ACTION STATUS MEETING i
September 19, 1989-j y:
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-I.aINTRODUCTION 1
- 11. PLANT ACTIVITIES A'.
Status ~.
B.
Recent Events / Issues III. SPECIAL TOPICS OF-INTEREST j;
A.
ADHRS JB...
Individual Plant Evaluation (GL 88-20)
C.
M0 VATS (GL89-10)-
D.
Light Loads E.
Tech Spec Improvement Program IV.: KEY-LICENSING ACTIONS A.
NRC Action B.
SERI-Action
~V.
OBSERVATIONS.REGARDING LICENSEE PERFORMANCE b
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KEY LICENSING ACTIONS I.
NRC ACTION - TECH SPECS A.
- RPS B.
Test, Vent and Drain Valves t
C.
SERI Organization /PSRC/SRC Composition D.. Combine STA/SR0 E.
-GL 87-09, TS 3.0.4 and 4.0.3 F.
Standby Liquid Control, Boron Concentration G.
Control Rod Testing H.
Consolidated Operating Company II. NRC ACTION - OTHER A.
Containment Purge Program i
C.
Pressure - Temperature Curve for R.G. 1.99 D..
Pipe Support Issues f
III. SERI ACTION - TECH SPECS A
Light Loads B.
Shutdown Cooling (ADHRS)
C.
Cycle Specific Variables
'D.
Relocation of RETS E.
Containment Purge (Pending NRC)
F.
Fire Protection Program (Pending NRC)
G.
Fire Protection - Addition of Smoke Detectors H.
Pressure - Temperature Cu;ve (Pending NRC) l NLSMISC89091501 - 2
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KEY LICENSING ACTIONS (Continued)
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IV. SERI ACTION - OTHER 1
8' A.
Inservice Testing Program Extension 10/3 (GL 89-04)
B.
Boraflex Gap - RAI 10/15 C.-
Individual Plant Evaluation (GL 88-20) 10/31 D.'
R.G.1.97 Neutron Monitoring System Report 10/31 E.
Surface Vehicle Bombs (GL 89-07) 11/8' F.
Motor Operated Valves - M0 VATS (GL 89-10) 12/22 09 G.
ASME Section III Procurement (GL 59-M)
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ENCLOSURE 3 GENERIC IEITER 89-09 ASME SECTION III 03@CNDff REPIACEMElGS l
Q (GGNS inplementation)
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k For a consistent inplementation of the NRC positions contained in Generic Istter 89-09 (GL), the following clarifications are provided.
1 In addition to replacement wupcrMits, the GL may also be applied to o
p e.,
cwyonent parts (i.e., disks, bonnets... ).
o When an item is procurred from a non-N-Certificate holder, an Authorized Nuclear Inspector will be assigned to the supplier's facility when the item fj is manufactured with pr=c-that require witnessing by an ANI. When ff 3-items are manufactured with processes that do not require witnessing by an ANI, the site ANII,s review of all associated documentation will satisfy-the requirements of ASME Section III.
o he FSAR will be revised to reflect the inplementation of GL 89-09.
AS an alternative to listing the GL 89-09 replacements in the FSAR, the ASME Section XI Repair / Replacement Summary Report (NIS-2) will drment the use
.NO of the GL.
Eis method of atterting ccupliance with the GL contains a certification statement frce the owner. Additionally, it bares a statement from the ANII.
For class 1 and 2 replacements this information is provided to the NRC in the ASME Section XI Sumary Report within 90 days of ccupleting each refuel outage.
o
% e NRC position says that the licensee must first establish that an
" equivalent"Section III stanped replacement is not available. GGNS understands this to have different meanings for ccrponents verses parts.
V 2e term " equivalent" regartling ccmponents inplies that an alternative I c-5 component can be obtained from an ASME N-Type certificate Holder that will fulfill the same safety function without physical design changes to the facility. Also, to qualify as equivalent, the replacement ccuponents operating parameters should imitate the original ocuponents to the extent that a new system or safety analysis is not required.
W e term " equivalent" for parts is more difficult for the owner to c5 define. Most ccmponents are designed by the ccmponent manufacturcr.
h e owner provides a design specification to the manufacturer that l-gives information for the components design. We owner, in all cases, i
may not be able to determine if a part made by another manufacturer possesses the same form, fit ard function abilities. With the recent concerns regarding counterfeit parts, it is believed prudent to obtain replacement parts from the original manufacturer (when available) rather than trying to match parts frca an alternative manufacturer.
When parts cannot be obtained frcn the original manufacturer, the replacement part will be obtained from an N-type certificate holder, when available.
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