ML20206E671
| ML20206E671 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 11/15/1988 |
| From: | Kintner L Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| GL-86-10, GL-88-12, IEIN-86-081, IEIN-86-81, NUDOCS 8811180158 | |
| Download: ML20206E671 (9) | |
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l November 15, 1988 DISTRIBUTION l
See attached sheet l
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' Docket No. 50-416 l
LICENSEE:
System Energy Resources, fac.
l FACILITY:
Grand Gulf Nuclear Station, Unt'. 1 i
SUBJECT:
SUNHARY OF NOVEMBER 1, 1988 MEETING REGARDING l
i FOTENTIAL CHANGES TO TECHNICAL SPECIFICATIONS 1
The NRC staff met with the licensee at the site to discuss potential changes te the Technical Specifications (TS) and other licensing action:. F d osure 1 is a list of participants. Enclosure 2 indicates some of the proposed TS changes, l
Following are comments regarding future submittals of TS changes:
f 1.
Generic Letter 88-12 regarding a new fire protection license condition and transfer of fire protection TS to the UFSAR.
Pages 1 and 2 of l
l indicate the proposed license condition and TS changes. The licensee proposed not to include the review by the Plant Safety Review l
Cosmittee(PSRC)ofthe"FireProtectionProgramandimplemeatingproce-dures and the submittal of recomrended changes" to the Corporate Safety i
ReviewCommittee(SRC). The Project Manager (PH) stated he would check I
with the appropriate NRR staff the following week.
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On November 10, 1988, the PM and ECEB staff talked to the licensee via telephone and advised that the license conditiot, should be the same as in i
GL 86-10 (the preceding fire protection guidance) and, thus, include. the date or Amenoment No. of the amended FSAR and revised UFSAR that contains the base line Fire Protection Program and the LCOs and Surveillance Requirements transferred from the TS.
In addition, the dates for the staff's SER, SER Supplement, and letters which approve this program will be included. Since these staff approvals will be a part of the license i
condition and therefore enforceable, the Itcensee should carefully review t, hem for accuracy before the license amendment is issued. The present
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itaff SER now in process will be sent via letter for an accuracy review prior to issuarce. Regarding the omission of the TS requirement for i
i raview of the Fire Protection Program by the PSRC and submittal of the i
changes to the SP.C. the licensee state:i that it believed present TS t
requirements for the PSRC to review 10 CFR 50.59 safety evaluationr should l
l be sufficient. The staff said that the GGNS 10 CFR 50.59 process i
presently included a screening process that screened cut many of the i
equipment and procedure changes and that, therefore, the words of Generic i
l Letter 88-10 should be used, which requires all changes to the fire l
l Protection Program t-be reviewed by the PSRC.
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. November 15, 1988 2.
LER 88-014 issued October 11, 1988 reported an isolation of the reactor water cleanup system (RWCU) because of a high delta flow signal during a l
system transient caused by changing from the postpump mode to the i
prepump mode.
Isolation of the RWCU during such transients has occurred l
several times (LER 87-009-0 and LER 88-004-01). The RWCU operatinq l
procedure has been changed to allow using bypass switches during such planned transients.
However, it is necessary to bypass other TS itws when bypassing the delta flow trip because of the way the circuitry is designed. The licensee is, therefore, proposing to install a keylock bypass switch for the delta flow trip for use during such transients.
The staff advised the licensee that a TS change would be required for the bypass s '.tch, becaure the proper interpretation of TS requires that ich trips not be bypassed except for surveillance tests.
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The licensee plans to submit a TS change request for a new auxiliary hoist to be installed on the fuel handling platform over the spent fuel pool.
Such a hoist is needed to handle control rods at the end of the i
spent fuel pool without removing platform stops 6..d railing as presently required. The new hoist would be identical to the one installed on the refueling platform in the containment. The submittal is scheduled for l
November 15, 1988.
4.
The licensee requested reconsideration of the current staff schedule (May l
30,1989) for review of the August 31, 1988 submittal regarding elimina-l tion of local leak rue testing for test, vent and drain lines less than I
one inch diameter.
The licensee has assumed approval of this submittal in i
its present refueling outage (schedule is to start March 1, 1989).
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outage would be ine. eased by two and a half to three days if the changes are not approved.
The licensee stated that only two plants have such requirements (C',1nton and Grand Gulf) and that the BWR Owners Group is not i
considering P. as i. generic item. The PM said he would arrange a conference all wi @ appropriate NRR staff regarding the possibility of improving the schedule.
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5.
The licensee will request a cbnge to Section 6.0 of the TS to allow the
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use of a combined STA/SRO position in the shift crew. The proposal will
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follow guidance in Generic Letter 86-04, and will be made within two months.
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The licensee plans to request an extension of the control rod block instrunentation surveillance interval as a part of the TS improvement
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Program within a few months, t
7.
The request to chan e TS Section 6.0 to delete references to specific positions in the un t organization and the corporate organization will be submitted within a few weeks.
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LER 88-016 issued October 21, 1988 advised the NRC o' a deficiency in the i
TS controlling movement of loads over spent fuel in the reactor during
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refueling and in the spent fuel pool at any time. The deficiency is that s
if loads lighter than a fuel assembly (1140 pounds) are dropped on irradiated fuel when secondary containe.ent is not required, the offsite
. November 15, 1988 dose consequences may not be bounded by currently analyzed accidents in the FSAR. The licensee has issued a standing order preventing loads to be carried over spent fuel in the spent fuel pool.
By February 1,1989, the licensee plans to cucplete a study of the consequences of such events and determine what administrative controls or TS changes are needed.
The staff said that if TS changes are needed prior to refueling activities, the proposed changes should be submitted by December 1,1988 to allow time for staff to review the proposal and issue amendments.
Following are comments regarding operational matters:
1.
In response to the PM's request, the licensee discussed actions taken to determine the cause and reduce the number of scrams (six in 1980).
Specific corre %1ve actions described in the LER's for the scrams include, design changus, disciplinary actions, training, procedure chang s, and labeling of equipment in the plant.
In addition, the following program.
r:atic tasks are in progresi.:
The scram reduction program started in 1987 is active. The ISEG is looking at reactor protection system actions to reduce sc:ams.
Design change packages associated with scram corrective actions get high priority.
A root cause analysis program which had been applied to all post trip reviews will be extended to other events.
INFO studies of human performance are considered.
2.
Regarding IN 86 81, supplement 1, which described failure of two addi.
tional MSIVs at Fermi because of spring failures, the licensee stated that its investigation showed that these two failures, like the four failures reported in IN 86 81, were all from a particular heat lot. No failures are expected at GGNS.1, which has springs from a different heat lot.
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Lester L. Kintner, Senior Projer.t Manager Project Directorate !!.1 Division of Reactor Projects 1/11
Enclosures:
As stated cc w/ enclosures:
See next page (GGNS HTG SUM!%RY 11 DRFR:DiPD21: p ::............::............:............:............::......-....
0FC :FH:FD NAME :LKi
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DATE : 11/ g f88
- 11/ D/88 OFFICIAL RECORD COPY
Mr. W. T. Cottle System Energy Resources, Inc.
Grand Gulf Nuclear Station (GGNS) cc:
Mr. T. H. Cloninger Mr. C. R. Hutchinson Vice President. Nuclear Engineering GGil5 General Manager and Support System Energy Resources, Inc.
System Energy Resources, Inc.
Post Office Box 756 P. O. Box 23054 Port Gibson, Mississippi 39150 Jackson, Mississippi 39205 Robert B. AcGehee, Esquire The Honorable William J. Guste, Jr.
Wise, Cartar, Child, Steen and Attorney General Caraway Department of Justice P. O. Box 651 State of Louisiana Jackson, Mississippi 39205 Baton Rouge, Louisiana 70804 flicholas S. Reynolds, Esquire Office of the Governor Bishop. Liberman, Cook, Purcell State of Mississippi and Reynolds Jackson, Mississippi 39201 1400 L Street, N.W.
Washington. 0.C.
20005-3502 Attorney General Gartin Building Mr. Ralph T. Lally Jackson, Mississippi 39205 Manager of Qvality Assurance Middle South Utilities System Mr. Jack McMillan, Director Services, Inc.
Division of Solid Waste Management 639 Loyola Avenue, 3rd Floor Mississippi Department of Natural flew Orleans, Louisiana 70113 Resources Post Office Box 10385 Mr. John G. Cesare Jackson, Mississippi 39209 Director, Nuclear Licensing System Energy Resources, Inc.
Alton B. Cobb, M.D.
P. O. Box 23054 State Health Officer Jackson, Mississippi 39205 State Board of Health P.O. Box 1700 Mr. C. B. Hogg, Project Manager Jackson, Mississippi 39205 Bechtel Power Corporation P. O. Box 2166 President Houston, Texas 77252-2166 Claiborne County Board of Supervisors Port Gibson, itississippi 39150 Mr. H. O. Christensen Senior Resident Inspector Regional Administrator, Region 11 U.S. Nuclear Regulatory Comission U. S. Nuclear Regulatory Comission Route 2 Box 399 101 Marietta Street 1
Port Gibson, liississippi 39150 Suite 2900 Atlanta, Georgia 30323 l
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t EHCLOSURE 1
!!0VEMBER 1,1988 NRC SERI H. Christensen
- 11. Crawford L. Kintner J. Fortenberry P. Simpson J. Fowler J. Roberston C. Angle 1
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ENCLOSURE 2 V"
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Insert to Operating License NPF-29 Section 2.C P
(41) Fire Protection Program SERI shall implement and maintain in effect ai l provisions of the approved Fire Protection Program as described in the Up ated Final Safety Analysis Report and as approved in the SER through Supp)Seent 7 subject to the following provision:
1 The Itcensee may make changes to the approved Fire Protection Program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve anJ maintain safe shutdown in the event of a firs.
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F J14 MISC 88101104 - 1 l
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NL'88/13 ADMINISTRATIVE CONTROLS i
UNIT STAFF (Continued)
I c.
A health physics technicirn' shall be onsite when fuel is in the
- reactor, d.
All CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation, e.o As Brigade of at least 5 rembers shall be mainta te at all times.
ire Brigade shall not inel ift t
(DELETED) e perintendent, the 5 other of the minimum shift u
I crew necessary for safe shut it, and any personnel required for other
,a functions dur ng mergen:y, At be available to respond to non-fire-S.
least one '
i w. %s from the Control Room.
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Administrative procedures shall be developed and implemented to limit the werking hours of unit staff who perform safety-related functions; i
e.g., senior reactor operators, reactor operators, health physicists, auxiliary operators, and key maintenance personnel.
Adequate s.df t coverage shall be maintained without ?outine heavy use of evertime, however, in the event that unforeseen problems recuire substantial amounts of overtime to be used, the following guidelines shall be followed:
l 1.
An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time, t
2.
An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hout period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour perico, nor ante than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any seven-day period, all excluding shift turrever time.
3.
A break of at least eight hovrs should be allowed between work periods, including shift turnover time.
4.
Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift.
Any deviation from the above guidelines shall be authorized by the GGNS G:neral Manager or his designee, or higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation.
Controls shall be included in the procedures such that individual overtime shall be reviewed monthly
- The number of health physics techniciansk
- NjbOpersonnel may be less than the minimum requirements for a perioc oTtime not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence provided innediate action is taken to fill the required positions.
GRAND GULF-UNIT 1 6-2 Amendment No. 45.,
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PS 88/02' 3
TABLE 6.2.2-1 PINIMUMSHIFTCREWCOMP051T10N POSITION NUMBER OF INDiv10 vat.5 REQUIRED To FILL POSlfl0N CONDITIONS 1,_2, & 3 CONDITIONS 4 & $
55 1
1 SRO 1
None RO 2
1 A0 2
1 ST O 1
None TABLE h3fATION 55 - Shift Superintendent with a Senior Reactor Operators License on Unit 1.
SRO Individual with a Senior Reactor Operators License on Unit 1.
RO - Individual with a Rear. tor Operators License on Unit 1.
AO - Auxiliary Operator.
STA - Shif t Technical Advisor.
Except for the Shif t Superintendent, the Shif t Crew Composition may be one less than the minimum requirements of Table 6.2,2-1 for a period of time not to esceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of onduty shift crew members provided immediate action is taken to restore the Shif t Crew Composition to within the minimum requirements of Table 6.2.2 1.
This provision does not permit any shif t crew position to be unmanned upon shif t change due to an oncoming shift cre, man being late or abseat.
During any absence of the Shif t Superintendent from the Control Room while the unit is in OPERATIONAL CON 0! TION 1, 2 or 3 an individual. ^^" ^" "'
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-Tettmfe*+ AG, i.vw with a valid SR0 license shall Le designated to assume the Control Room command function.
During any absence of the Shift Superintendent from the Control Room while the unit is in OPERATIONAt CONDITION 4 or 5, an ino!vidual with a valid SRO or R0 license shall be designated to assume the Control Room command function.
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?~, reqaired by Section 6.3, may also serve as the STA. If this option is used for a shift, then the separate STA position may be eliminated for that shift.
m GRAND GULF-UNIT 1 6-5 Arendment No.
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DISTRIBUTION FOR !!EETING SUM!tARY DATED: November 15, 1988 Facility: Grand Gulf Nuclecr Station Unit I tDA ket File-:
HRC POR Local PDR PDll-1 Reading E. Adensam P. Andersen L. Kintner OGC E. Jordan (P.NBB3302)
B. Grimes (9A?)
ACRS (10)
P.,Dorchardt(17D19) cc: Licensee / Applicant Service List I
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