ML20073P906
| ML20073P906 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 05/16/1991 |
| From: | Cottle W ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GNRO-91-00057, GNRO-91-57, IEB-90-001, IEB-90-1, NUDOCS 9105240083 | |
| Download: ML20073P906 (9) | |
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A : Entcrgy
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Operations W.T.cotu.
l May 16, 1991 U.S. Nuclear Regulator y Conunission Mall Station pl-137 Wa s h i tigt on.
D.G.
20555 At t eut lons
!)oc ume n t Cont i ol Desk
Subject:
Grand Guli Nuclear Statlon Util t 1 Docket No. 50-416 1.lcense No. N 1'F-2 4 Addltlonal Information Re1ated to NRC Bulletin 90-01 GNRO-91/00057 Gent lemen:
This submit t al provides additional information for Grand Gulf Nuclear Station (G6NS) related to NRC Bulletin 90-01
" Loss of Fill-Oli in Transmitters Manufactured by Rosemount." Our initial response to this Bullet in was provided by let t er dat ed July 19, 1990 (AECM-90/0128).
At the request of the GGNS NRC project Manager, additional inf ormat ion beyond that speci fied by t he liullet in was provided by let t er dated September 12, lu90 (ALCM-40/0105).
In accordance with the schedule provided in our July 19, 1990 submittal, 27 GGNS Rosemount t ransm! t t ers irom manufacturing lots identifled by Rosemount as having a high f ailure f ract ion due to fill-oll loss were replaced during the f our t h ref ueling out age.
One additional t ransmit ter f rom these manuf acturing lots has been recently identified, and has been documented as acceptable for interim use.
Monitoring of this t ransmitter will continue as provided in the previously est ablished enhanced surveillanen program discussed in unt il it is replaced during t he upcoming f if t h refueling outage.
This addit ional t ransmit ter was not included in the original list provided t o GGNS by Rosemount of manufacturing lots with a high failure fraction due to fill-oll loss, and was Inst alled prior to our receipt of a supplemental list of additional lot numbers from Rosemount.
plant records f or t his new t ransmit ter were not yet updat ed when the GGNS review of these additional lot numbers identified by Rosemount was performed.
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May 16, 1991 GNRO 91/00057 Page 2 of 3 Although not from lots ident ified as having a high failure f raction due to fill-oil loss, we have identified en additional fifteen Rosemount transmitters which fall within the scope of the liulletin.
The original comput.cr searches of GGNS records did not locate the fifteen transmitters due to errors in the perfortnance of the search and/or in the coding of vendor itiformat ioti in database records.
We are in the process of implementing correct ive actions to address our influte to init int ly ident ify all npplienble t rnnsmit t ers.
Additionni reviews have been performed to ensure that all t ransmitters within the scope of NRC Hullet in 90 01 are incinde.1 in this submit tal.
The At tachtnent s have been updat ed t o reflect changes to the information in the previous submittals.
Changes are denoted by a bar in the right inntgin of each At tachment.
This information is being submitted under affirmation in accordance with 10CFR50.54(f).
Please cont act 11. E. Kook (60: 437-6477) should you have any questions or need addit ional information regarding t his matter.
Yours truly, w
7~~' Csr rr~~
WTC/IIEK/cje attachments: NRCD 90-01 Response Information cc:
Mr. D. C. Ilintz (w/n)
Mr. J. Mathis (w/n)
Mr. R. B. McGehen (w/n)
Mr. N. S. Reynolds (w/n)
Mr. II.
I,.
Thomas (w/o)
Mr. F. W. Titus (w/a)
Mr. St ewart D. Ebnet er (w/a)
Regional Administrator ti.S. Nuclear Regulatory Commission Region 11 101 Harlett a St., N.W., Srit.e 2900 l
At.lanta, Georgin 30323 Mr. L. L. Kintner, Project Manager (w/a) of fice of Nuclear Reactor Regulation U.S. Nuclear Regulatory Cornmission Mail Stop llD21 Washington, D.C.
20555 Mr. Alex Marion (w/a)
Nuclear Manngement and Resources Counci1 l
1776 Eye Street, N.W., Suite 300 Washington, D. C. 20006 09103271/SNLICFLR - 2
11EFORE Tile UNITED STATES NUCLEAR REGULATORY COMMISSION LICENSE NO. NPF-29 DOCKET No. 50-416 IN THE MATTER OF MISSISSIPPI POWER & LIGHT COMPANY and SYSTEM ENERGY RESOURCES, INC.
and SOUTil MICSISSIPPI ELECTRIC POWER ASSOCI ATION and ENTERGY OPERATjoNS, INC.
AFFIRMATION 1, W. T. Cottle, being duly sworn, state that I am Vice Prealdent, Operations GGNS of Entergy Operations, Inc.; that on behalf of Entergy operations, Inc., System Energy Resources. Inc., and South Mississippi Electric 'ower Association I am authorized by Entergy Operations, Inc. to sign and file with the Nuclear Regulatory Conunission, this additional informati(n for the Grand Gulf Nuclear Station related to NRC Bulletin'50-01: that I signed this letter and affirmation as Vice President, Operations GGNS of Entergy Operations, Inc.; and that the statements made and the mat.ters set forth therein are true and correct to the best of my knowledge, information and belief.
Wy f." M-W. T. Cottle STATE OF MISSISSIPPI COUNTY OF CLAIBORNE l
SUBSCRIBED AND SWORN To before me, a Notary Public, in and for the County and State above named, this 4
day of tYW,
1991.
(SEAL) cibuh Ubhnh NotaryJibl]
My conunission expires 0 kamsen f.sp.: J4 3, ign l
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4 Attachment I t o GNRO-91/00057 Page 1 of 3 Grand Gulf Nuclear Station NRC Bulletin 90-01
" Reporting Requirements for Operating Reactors **
NRCB Item Grand Gulf Nuclear Station Response 1.a)
Grand Gulf Nuclear Station (GGNS) confirms that items 1, 2, 3,
4, and 5 of NRC Bullet in (NRCB) 90-01 Requested Act ions for Operating Reactors have been completed as stated belows Request ed Act lons, 11em 1-GGNS has identified Models 1153 Series B, 1153 Series D.
and 1154 pressure and differential pressure t ransmit ters manufactured by Rosemount prior to July 12, 1989, t hat. are currently ut.111 zed in either safety-related systems or systems installed in accordance with 10CFR$0.02 (the ATWS rule). ** 152 of these af fect ed t ransmit ters were determined to have been installed at GGNS, with 33 of the 152 replaced during the recent fourth refueling outage.
Requested Actlons, Itom 2-GGNS has determined that 28 of the 152 affected transmitters were from manufacturing lots identified by Rosemount as having a high failure fraction due to the loss I
of fill-oil.
GGNS has replaced 27 of these transmitters during the recent fourth refueling outage ***.
The current schedule is for the additional transmitter to be replaced by the end of the upcoming fifth GGNS refueling outage.
This outage is presently scheduled to begin approximately April 1992.
Requested Actlons, i tem 3-GGNS plant records have been reviewed to determine if any of the 152 af fected t ransmitters may have already exhibited symptoms Indicative <~ fill-oil loss.
This review was consistent with the guidance of NRCB 90-01 and Rosemount Technical Bulletin Number 4.
As a tesult of the review, it I
was determined that none of these currently installed GGNS transmitters have f111-o11 loss.
Previously installed I
transmitters which have experienced fill-oil loss are discussed in NRCh item 1.b).
Previous ly Attach'nent 1 to AECM-90/0128.
- Referred to hereaf ter as the "af fected t ransmitters."
Six additional transmitters within the scope of NRCB 90-01 which were net from the manufacturing lots ident ified wit h high f ailure l
fractions were also replaced during this outage.
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At t achinent 1 to GNRO-91/00057 page 2 of 3 Requested Actlons. It cm 4-GGNS has developed and implemented an enhanced survolllance progt am t o monitor the af f ect ed t ranstnit t ers for symptoms of fill-oll loss.
The program is consistent with the guidance of NRCB 90-01 and Rosemount Technical Bulletin i
Number 4.
Request ed Act Iens, I t o m *i-A basis fot continued plant operation was documented covering the tirne until the 27 transmitters discussed in NRCD 90-01 Requested Actlons. Item 2 were replaced.
This basis has been updat ed to cover t he addit ional " suspect lot" t ranstnit t er (11121N095B).
Based on Information determined from the reviews discussed above. and t hat in NRCD 90-01 and Rosemount Technical Bulletin Number 4 the use of this transmitter was found to be acceptable until its replacement.
Replacement Jr. now scheduled during the upcoming fifth refueling outage.
' Ibis outage is scheduled to begin approximately April 1992.
NRCD Item Grand Gulf Nuclear Station Response 1.b)
As a result of the review of plant records discussed in NRCD ltem 1.a), item 3. no curretit ly Installed GGNS transmitter has been identified with fill oil loss.
Informat Un regarding four GGNS t ransmitters previously identified with fill-oll loss is presented in Attachment 2.
These four transmitters were replaced before March 1988, whleh was prior to the issuance of NRCD 90-01 and NRC Inf ormat lon Not Ice 89-42 "Fallure of Rosemount Models 1153 and 1154 Transmitters." No other GGNS transmitters are known to have experienced fill-oil loss.
NRCD Item Grand Gulf Nuclear Station Resfonse 1.c)
There were 28 affected transmitters installed in GGNS from manufacturing lots identified by Rosemount as having a high failure fraction due to loss of fill-oil.
27 of these t ransmit ters were replaced during the recent f ourt h refueling outage.
The final t ransmit t er 18 currently scheduled for replacement during the upcoming iif th GGNS refueling out age.
This outage is scheduled t o begin approximately April 1992. The plant system in which each of these transmitters is installed is identified in i'.
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I Attachment I to GNRO-91/00057 Page 3 of 3 i
NRCD Grand Gulf Nuclear Station Response l
2.
Rosemount Models 1153 Series 11 1153 Series D, and 1154 transmitters which are suspected or confirmed to have f111-o11 loss will be documented as nonconformances and returned to Rosemount for failure analysis.
As part of this process, data similar to that in Reporting Requirement item 1.b) will be recorded.
Reportsbility reviews under existing NRC regulations will be conducted as part of the nonconformance process.
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At tachment 2 t o GNRO-91/00057 page 1 of 1 Grand Gulf Nuclear Station NRC Bulletin 90-01 "GGNS Transmitters Identified with F111-011 Loss"*
Transmitter Approximate Number /
Indicated System Time at Corrective Serial No.
Hanufacturer Number Pressure Action / Disposition B21-N073L**
Fosemount b21***
9 months Replaced in Decernber 1983
/412017 af ter mismatch between channels was found during operational rounds channel check.
B21-N001F**
Rosemount 112 1 * *
- 15 inonths Replaced in June 1986
/412022 after mismatch between channels was found during operatlonal rounds channel check. ****
B21-N091B**
Hosemount 112 1 * *
- 28 months heplaced in July _1987
/412020 after mismatch bet u en channels was found during operational rounds channel check. ****
B21-N091F**
Rosemount 112 1* *
- 20 months Replaced in February 1988
/412029 after mismatch between channels was found during operational rounds channel check. ****
Previously Attachment. 2 to AECM-90/0128.
'** Model Number 1153DD5.
System B21 _ Nuclear Steam Supply and Related Instrumentation.
- This transmitt er was returned to Rosemount for failure analysis af ter replacement, l-09103271/SNLICFLR - 8 l
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- s t o GNRn-91/00057 l
16ge 1 of 1 Grand Gulf Nuclear Station NRC Bulletin 90-01 "Affected Transmitters from Manufacturing Lots Identified by Rosemount with a liigh Failure Fraction due to F111-011 Loss"*
Transmitter Hodel Transmitter Number Number fystem IB21N062A**
1153GD9 li21-Nuclear St eam Supply and Relat ed I;ist rument at ion 1821N067C**
1153AD5 B71-Nuclear St eam Supply and Relat ed Inst rumentat ion IB21N067G**
1155AD5 it21-Nuclear Steam Supply and Related lusttumentation 1B21Ne67L**
1153AD5 li21-Nuc l e a t Steam Supply and Related Instrumentation 1B21N067R**
1153 ADS B21-Nu(lear St cam Supply and Related itst rumentatlon IB21N073C**
1153DD5 B21-Nuclear Steam Supply and Related Instrumentallon 1B21N073G**
1153DDS Il21-Nuclear Steam Suppl:/ and Relat ed inct rtunentation 1B21N073L**
1153DD5 B21-Nuclear Steam Supply and Related Inst rtunentation 1B21N073R**
1153DD5 B21-Nuclear St eam Supply and Relat ed Inst riunentat lon 1B21N076C**
1153GD9 B21-Nuclear Steam Supply and Related Instrumentation 1B21N091A**
1153DD5 B21-Nuclear Steam Supply and Relat ed Inst rumentation 1821N091B**
1153DDL lt21-Nuclear Steam Supply and Related Instrumentation IB21N091E**
1153DD5 It21-Nuclear Steam Supply and Related Instrumentation IB21N091F**
1153DD5 B21-Nuclear Steam Supply and Related Instrumentation 1B21N094A**
1153AD5 B21-Nuclear Steam Supply and Relateu Ins t rumentat ion 1B21N094B**
1153AD5 B21-Naclear Steam Supply and Related Inst runwntation 1B21N094E**
1153AD5 B21-Nuclear Steam Supply and Related Instrumentation 1B21N094F**
1153AD5 B21-Nuclear Steam Supply and Related lustrumentation IE12N007A**
1153DD5 E12-Residual lleat Removal System 1E12N007B**
1153DDS E12-Residual Heat Removal System 1E12N015A**
1153DD5 E12-Residual lleat Removal System 1E12N015B**
1153DD5 E12-Residual lleat Removal System 1E12N015C**
1153DD5 E12-Residual lleat Removal System 1E12N062A**
1153 ADS E12-Residual lleat Removal System 1E12N062B**
1153Ab5 E12-Fesidual lleat Removal System 1E12N062C**
1153AD5 E12-Reridual lleat Removal System 1E12N062D**
1153 ADS E12-Re sidual lleat Removal System IB21N095B***
1153DD4 B21-Nuclear Steam Sup ly and Related Instrumentation Previously Attachment 3 to AECM-90/0128.
Replaced with "non-suspect lot" transmitter during the fourth refueling outage.
- Scheduled for replacement in the fifth refueling outage.
G9103271/SNLICFLR - 9
.. to GNRO-91/00057 l
Page 1 of 1 I
Grand Gulf Nuclear Station NRC Bulletin 90-01
" Additional Information on ' Suspect Lot' Transmitters"*
Transmitter Serial Mumbor Number **
ESF/RPS Transmitter Function 1B21N062A 411859 N/A FPV Pressure - Accident monitoring only, no ESF or PS actuation function 1B21N067C 411865 ESF liPCS Drywell Pressure IB21N067G 411866 ESF llPCS Drywell Pressure 1B21NJ67L 412005 ESF llPCS Drywell Pressure 1B21N067R 412006 ESF llPCS Drywell Pressure IB21N073C 412015 ESF llPCS Level IB21N073G 412016 ESF llPCS Level 1B21N073L 412028 ESF llPCS Level 1B21N073R 412030 ETF llPCS Level IB21N078C 411863 ESF &
Shutdown Cooling isolation & Level 3 RPS Scram IB21N091A 412019 ESF Reactor Vessel Water Level 1B21N091B 412033 ESF Reactor Vessel Water Level IB21N091E 412021 ESF Reactor Vessel Water Level 1B21N091F 412031 ESF Reactor Vessel Water Level 1B21N094A 412007 ESF Drywell Pressure 1B21N094B 412008 ESF Drywell Pressure 1B21N094E 412009 ESF Drywell Pressure IB21N094F 412010 ESF Drywell Pressure 1E12N007A 412023 N/A RilR lleat Exchanger Flow - in an ESF System, but has no ESF actuation function 1E12N007B 412024 N/A 1E12N015A 412025 N/A RilR Flow - in an ESF System, but has no ESF actuation function IE12N015B 412026 N/A 1E12N015C 412027 N/A 1E12N062A 412h11 ESF Contalnment Spray 1E12N062B 412u12 ESF Containment Spray 1E12N062C 412013 ESF Containment Spray 1E12N062D 412014 ESF Containment Spray 1821N095B 412035 ESF Vessel Narrow-Range Level-ADS B Previously Attachment to AECM-90/0165, Serial numbers of eriginal " Suspect Lot" transmitters; all replaced in the fourth refueling outage except for IB21N095B, which is scheduled for replacement in the fifth refueling outage.
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