ML18096B336

From kanterella
Jump to navigation Jump to search
Forwards Response to Suppl 1 to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. Enhanced Surveillance Program for Transmitters,Consisting of Drift Monitoring & Channel Checks,Developed
ML18096B336
Person / Time
Site: Salem, Hope Creek  PSEG icon.png
Issue date: 03/05/1993
From: Hagan J
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
IEB-90-001, IEB-90-1, NLR-N93032, NUDOCS 9303150124
Download: ML18096B336 (54)
v • d • e


Text

t.

-PS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Nuclear Department MAR 0 5 1993 NLR-N93032 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555_

Gentlemen:

RESPONSE TO NRC BULLETIN 90-01, SUPPLEMENT 1 HOPE CREEK AND SALEM GENERATING STATIONS FACILITY OPERATING LICENSES NPF-57, DPR.;...'70 AND DPR-75 DOCKET NOS *. 50-354, 50-272, AND 50-311 Public Service Electric & Gas Company (PSE&G), in accordance with Bulletin- 90-01, Supplement 1, has reviewed Salem and Hope Creek plant records and, with regard to the Reporting Requirements of the subject Supplement, provides the following summary:

1. PSE&G will take the requested_ actions for the Salem and Hope Creek Stations. *
2. Enclosure 1 provides detailed responses to your Reques~ed Actions for our Salem Generating Station, Unit Nos .. 1 and 2.

Enclosure 2 responds, in detail, to the Bulletin's Requested Actions for our Hope Creek Generating Station.

3. PSE&G is not taking exception to any requested action for the Salem or Hope Creek Generating Stations.

Should you have any question regarding this response, we will be pleased to discuss*it with you.

Sincerely, 120008' 9303150124 930305 PDR Q

ADOCK 05000272 i 1ic' i'\ '\\*:_T is ni \\1ur nancL PDR

{Y6Jq I 95*2168 REV. 11/91

., I

1

. /

Document Control Desk MAR 0 5 1993.

NLR-N93032 Enclosures Affidavit c Mr. T. T. Martin, Administrator - .USNRC Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King.of Prussia, PA 19406 Mr. J. c. Stone, *Licensing Senior-Project Manager U.S. Nuclear Regulatory Commission One White Flint North (MS 14 E-21) 11555 Rockville Pike Rockville, MD 20852 Mr. s. Dembek, Licensing Project Manager U.S. Nuclear Regulatory Commission

.One White Flint. North (MS 14 E-21) 11555 Rockville Pike Rockvi*lle, _MD 20852 Mr. T. P. Johnson USNRC Senior Resident Inspector Mr. K. Tosch, Chief, New Jersey Department of Environmental Protection and Energy Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625

-~. I

_/ .

REF: NLR-N93032 STATE OF*NEW JERSEY

  • SS.

COUNTY OF SALEM Joseph J. *Hagan*, being duly sworn according to law deposes and says:

I am Vice President Nuclear Operations of Public Service*

Electric and Gas Company, and as such, I find the matters set forth in the above referenced letter concerning the Salem Generating Station and Hope Creek Generating Station are true to the best of my knowledge, information and belief.

me 1993

. KIMBERLY A. Hl~l 1 _

NOTARY PUBLIC qF NEW .,t:RSEY My Commission Expires March 9, 1997 My Coirunission expires on

~~-----------

Reference:

NIR-N93032-ENCUH1RE 1 salem plant records were reviewed arxi all installed Rc:lselool.mt Model 1153, Series B, M:x:iel 1153, Series D, arxi Model 1154 transmitters tnanufactured before July 11, 1989 were identified. 'Il1is constituted the basic data set ;for which the evaluation was performed. A detailed :reView of the data set was perfonned based upon specific actions requested in the bulletin with transmitters categorized by safety function, normal operating pressure ranges, -

arrl psi-nonth criteria. 'Ihe results of this review, are presented below, following the outline of the Requested Actions of the B.11.letin SUpplernent.

Additionally, salem warehouse Rosemount ilwento:ry was walked-down, reviewed for bulletin applicability, arxi (since all i.nvento:ry serial numbers were greater than 500000) found to be exerrpt.

1(a) RPS, ~- arD. MW> Transmitters> 1500 p;i A total of 14 transmitters were identified which fell into this catego:ry.

All 14 transmitters are installed in Unit 2 arrl had-been previously scheduled for replacement with Rosem::>unt transmitters manufactured after -

July 11, 1989, having a serial mnnber greater than 500000. 'lhese transmitters (See Attachment 2, page 4) are scheduled for replacement in the upcaming 2R7 outage.

1 (b) other Safety-Related .AR>licatiais > 1500 p;i -

A total of 6 transmitters were identified in this catego:ry. All of the 6 met the psi-m:>nth threshold. Justification for extension of the quarterly test inteJ:val to once per 18 nonths is based upon the enhanced surveillance program, detailed in (2) below.

1(c) [Far Ams] RPS, ~. arxi A'DE Transmitters> 500 p;i 5 1500 p;i, (psi-nort:h threslx>ld IDt met)

A total of 20 transmitters were identified which fell into this catego:ry.

16 of the 20 transmitters had been previously scheduled for replacement with transmitters marrufactured after July 11, 1989, having a serial rn.nnber greater than 500000 (See Attactnnent 2, page 3). Of the four transmitters remaining (Attachnent 1, page 11 & Attachmant 2, page 4),

two transmitters for Unit 2 will be replaced i.'1 t.lie upcaming 2R7 outage am.the remaining two transmitters will be placed on the Unit 1 forced outage 'INOrk list for :replacement.

1 (d) other Safety-Related AR>licaticms > 500 psi 5 1500 psi, (psi""ilD1th threshold net met)

No transmitters were identified in thiS categoi::y.

1(e) Hen-RPS, ~- and~ Transmitters> 500 psi 5 1500 psi, (psi-nort:h threshold met) - '

A total of 35 transmitters were identified which fell into -this categoi::y. No action is required for these components; hc:MeVer, Salem will continue tO include them in the enhanoed su:rveillance program.

1(f)_ Any Safety-Related Transmitters 5 500 psi A total of 54 transmitters were identified which fell into this categoi::y. No action -is required for these components; however, Salem will continue to inClude them in the enhanced surveillance program.

'!he enhanced surveillance program for the transmitters that are part of this evaluation follows the calibration data tren:iing recarmnendations presented by Roserociunt in their published "Technical Bulletins". '!his enhanced Smv-eillance program, -follOVlin;J manufacturer recarmnendation, will provide the necessary data and the high degree of confidence required for detection of degradation caused by loss of fill-oil.

Transmitters with a serial number greater than 500000 are excluded from

, the enhanoed .surveillance program. '!he enhanced rronitoring *program at Salem consists of the followin;J:

t Drift Monitoring All transmitter zero drift is trerde1 anJ. analyze1 in accordance with the Roserrount Technical Bulletin guidelines.

t Transient Response Monitoring calibration of the transmitters includes observation of the transmitter for a sluggish transient response.

'!he operating staff performs channel checks in acx::ordance with Technical Specification requirements. Deviation from channel to channel is_ noted and investigated. Degradation can be rronitored in this -:manner.

I I

  • Process Noise Monitoring Transmitter prcx:::ess noise analysis is an available tool to m:>nitor a questionable transmitter while it is in service.
1. Salem will take the actions requested.
2. . With regard to the above actions:
a. *'!he actidns that Salem will cornplete to meet Item 1 of the Bulletin SUpplement's Requested Actions are detailed in Attadnnents 1 arrl 2 arrl in the. E'VAIIJATION OF ~ ACI'IONS Section of this Enclosure.
b. '!he scbedule for cornpletion of the Item 1 Requested Actions is also provided in Attachments 1 arrl 2 arrl in the EVAIIJATION OF REX2UIRED ACI'IONS Section of this Enclosure.
c. PSE&G will ocnfb:m, upon their completion, that Items 1 arrl 2 of the Bulletin SUpplerrent Required Actions have been ccmpleted.
3. Not applicable - PSE&G is taking no exception to the requested actions. *, -

ATTACHMENT 1 SALEM UNIT 1 ROSEMOUNT OIL LOSS RESPONSE TO NRC BULLETIN 90-01, SUPPL. 01 IPT455. 9 1154SH PressurizerPressure YES.* NO NOACTIONREOUIRED. Transmitterwas manufactured after July 11, 1989. This was confirmed by verifying installed transmitter's serial number being greater than 500000. Therefore, transmitter does not fall into NRC Bulletin 90-01, Suool. 01 criteria.

IPT456 9 1154SH Pressurizer Pressure YES NO See same justification for 1PT455.

1PT457 9 1154SH Pressurizer Pressure YES NO See same justification for 1PT455.

  • Pressurizer Pressure YES NO See same justification for IPT455.

1LT459 5 1154HH Pressurizer Level . YES NO See same justification for 1PT455.

ILT460 5 1154HH Pressurizer Level YES NO See same justification for 1PT455.

1LT461 5 1154HH Pressurizer Level YES NO See same justification for 1PT455.

  • 1FT512 5 1154HH Steam Generator Flow YES NO See same justification for 1PT455.

IFT513 5 1154HH Steam Generator Flow. YES NO See same justification for 1PT455.

IFT522 5 1154HH Steam Generator Flow YES NO See same justification for 1PT455.

IFT523 5 1154HH Steam Generator Flow . YES NO See same justification for 1PT455.

1 1FT532 5 1154HH Steam Generator Flow YES NO See same justification for 1PT455 ..

IFT533 5 1154HH Steam Generator Flow YES NO See same justification for 1PT455.

IFT542 5 ll54HH Steam Generator Flow YES NO See same justification for 1PT455.

1FT543 5 1154HH Steam Generator Flow YES NO See same justification for 1PT455.

1LT501 5 U54HH Steam Generator Wide YES NO See same justification for IPT455.

Ran~eLevel 1LT502 .5 1154HH Steam Generator Wide Range Level YES NO See same justification for 1PT455.

9*

1LT503 5 1154HH Steam Generator Wide YES Nb See same justification for IPT455.

Range Level I '

1LT504 5 1154HH Steam Generator Wide YES. NO See same justification for 1PT455.

Range Level 1LT517 . 4* 1154HH Steam Generator YES . NO See same justification for 1PT455.

Narrow Range Level 1LT518 4 1154HH Steam Generator YES NO See same justification for 1PT455.

Narrow Ran~e Level 1LT519 4 1154HH Steam Generator YES 1'10 See same justification for 1PT455.

Narrow Ran~e Level 1

ATT A CHM ENT 1 SALEM UNIT 1 ROSEMOUNT OIL LOSS RESPONSE TO NRC BULLETIN 90-01, SUPPL. 01 i-**----

ILT527 1LT528 4

4 l 154HH ll54HH Steam Generator Narrow Range Level Steam Generator Narrow Range Level YES YES NO NO See same justification for 1PT455.

See same justification for 1PT455.

1LT529 4 1154HH Steam Generator YES NO See same justification for 1PT455.

Narrow Range Level 1LT537 4 1154HH Steam Generator YES NO See same justification for 1PT455.

Narrow Range Level 1LT538 4 ll54HH Steam Generator YES NO See same justification for 1PT455.

Narrow Range Level 1LT539 4 1154HH Steam Generator YES NO See same justification for 1PT455.

Narrow Range Level 1LT547 4 1154HH Steam Generator YES NO See same justification for 1PT455.

Narrow Range Level 1LT548 4 1154HH Steam Generator YES NO See same justification for 1PT455.

Narrow Range Level 1LT549 4 1154HH Steam Generator .YES NO See same justification for 1PT455.

Narrow Range Level 1PT514 9 1154SH Steam Generator YES NO See same justification for 1PT455.

Pressure 1PT515 9 1154SH Steam Generator YES NO See same justification for 1PT455.

Pressure 1PT516 9 1154SH Steam Generator YES NO See same justification for 1PT455.

Pressure 1PT524 9 1154SH Steam Generator YES NO See same justification for 1PT455.

Pressure 1PT525 9 1154SH Steam Generator YES NO See same justification for 1PT455.

Pressure 1PT526 9 1154SH Steam, Generator YES NO See same justification for 1PT455.

Pressure 2

ATTACHMENT 1 SALEM UNIT 1 ROSEMOUNT OIL LOSS RESPONSE TO NRC BULLETIN 90-01, SUPPL. 01

  • 11t11**----

1PT534 1PT535 9

9 l 154SH 1154SH Steam Generator Pressure Steam Generator YES YES NO NO See same justification for 1PT455.

See same justification for 1PT455.

Pressure 1PT536 9 1154SH Steam Generator YES NO See same justification for 1PT455.

Pressure 1PT544 9 1154SH Steam Generator YES NO See same justification for 1PT455.

Pressure IPT546 9 1154SH Steam Generator YES NO See same justification for IPT455.

Pressure 1PT403 9 1154SH Reactor Coolant YES NO See same justification for 1PT455 ..

Pressure '

IPT405 9 1154SH Reactor Coolant YES NO See same justification for IPT455.

Pressure 1Ff414 5 1154HH Reactor Coolant Flow YES NO See same justification for IPT455.

1Ff415 5 1154HH Reactor Coolant Flow YES NO See same justification for IPT455.

1Ff416 5 1154HH Reactor Coolant Flow YES NO See same justification for IPT455.

1Ff424 5 1154HH Reactor Coolant Flow YES NO See same justification for 1PT455.

1Ff425 5 1154HH Reactor Coolant Flow YES NO See same iustification for 1PT455.

1Ff426 1Ff434 1Ff435 5

5 5

1154HH 1154HH 1154HH Reactor Coolant Flow Reactor Coolant Flow Reactor Coolant Flow YES YES YES NO NO NO See same justification for 1PT455.

. See same justification for IPT455.

See same justification for 1PT455.

e 1Ff436 5 1154HH Reactor Coolant Flow YES NO See samojustification for.IPT455.

1Ff444 5 1154HH Reactor Coolant Flow YES NO See same justification for 1PT455 ..

1Ff445 5 1154HH Reactor Coolant Flow YES NO See same justification for 1PT455.

1Ff446 5 1154HH Reactor Coolant Flow YES NO See same justification for IPT455.

1LT935B 4 1153HD Accumulator Level YES NO See same justification for 1PT455.

1FA1091 5 1153HD Auxiliary Feedwater YES NO See same justification for 1PT455.

Flow 1LT920 5 1153HD Reactor Water Storage YES NO See same justification for 1PT455.

Taruc Level 1LT921 5 1153HD Reactor Water Storage YES NO See same justification for 1PT455.

Taruc Level 3

ATTACHMENT 1 {.

SALEM UNIT 1 ROSEMOUNT OIL LOSS RESPONSE TO NRC BULLETIN 90-01, SUPPL. 01 1LT470 4 1153DD Pressurizer Relief Tank Level NO NO The transmitter meets the same justification for 1PT455, however. it*is used in a NON-SAFETY RELATED function. Therefore, exempt from NRC Bulletin 90-01, Suool. 01 *criteria.

1LT1003 4 1153DD Reactor Coolant Drain. NO NO 'The transmitter meets the same justification for Tank Level 1PT455, however. it is used in a NON-SAFETY ~

RELATED function. Therefore, exempt from NRC ._

Bulletin 90-01. Sunni. Ol.criteria.

1LT1641 4 1153HD Steam Generator YES NO See same justification for 1PT455.

Narrow Range Level

<Hot Shutdown)

ILT16273 4 1153HD RHR Mid-Loop Level YES NO See same justification for 1PT455.

1LT16274 4 1153HD RHR Mid-Loop Level . YES NO See same justification for 1PT455.

1PT16272 5 1153GD RHR Mid-Loop YES NO See same justification for 1PT455.

Pressure 1PT16275 5 1153GD RHR Mid-Loop YES NO See same justification for 1PT455.

Pressure 1LT934A 4 ll53HD Accumulator Level YES . 1.E NO ACTION REQUIRED. CONTINUE ENHANCED MONITORING ONLY. Although transmitter was manufactured before July 11, 1989, transmitter has reached it's PSI-MONTH criteria of>60.000 psi-month with a normal operating pressure within the boundaries of>500 psi and <1500 psi. The maturity of the transmitter indicates that the transmitter will achieve a high funCtional reliability, Additionally, previous trending data (zero and span shift evaluation) has assured PSE&G that the ~smitter has beCn a good performer and supports Rosemount and NUMARC's conculsion on transmitter health/performance as it

  • relates to psi-month criteria. Therefore, transmitter does not need to be replaced or enhanced monitoring performed. However. PSE&G will continue to monitor the transmitter in order to maintain a high degree of .

confidence for detecting failure due to loss of fill-oil.

4

  • ATTACHMENT 1 .I,_

SALEM UNIT 1 ROSEMOUNT OIL LOSS RESPONSE TO NRC BULLETIN 90;.01, SUPPL. 01 ILT934B 1LT934C 1LT934D lLT935A 4

4 4

4 ll53HD ll53HD 1153HD 1153HD Accumulator Level Accumulator Level Accumulator Level Accumulator Level YES YES YES YES l.E 1.E l.E 1.E See same justification for 1LT934A.

See same justification for lLT934A.

See same justification for 1LT934A.

See same justification for 1LT934A.

lLT935C 4 ll53HD Accumulator Level YES 1.E See samejustification for 1LT934A.

1LT935D 4 ll53HD Accumulator Level YES 1.E See same justification for 1LT934A.

1PT508 9 ll53GD Steam Generator Feed NO NO The transmitter meets the same justification for Pump Header Pressure lLT934A, however. it is used in a NON-SAFETY RELATED function. Therefore, exempt from NRC Bulletin 90-01, Sunni. 01 criteria.

lFT918 6 ll53HD Safety Injection Pump YES 1.E Seesamejustificationfor lLT934A.

Discharge Flow (achieved> 130,000 psi-month Rosemount criteria)

IFT922 6 ll53HD Safety Injection Pump YES 1.E See same justification for 1LT934A.

Discharge Flow (achieved > 130,000 psi-month Rosemount criteria) 1FA1087 5 ll53HD Auxiliary Feedwater YES l.E See same justification for 1LT934A.

Flow IFA1095 5 1153HD Auxiliary Feedwater YES 1.E See same justification for ILT934A.

Flow IFA1097 5 1153HD Auxiliary Feedwater YES l.E, See same justification for 1LT934~.

Flow 5

ATTACHMENT 1 SALEM UNIT 1 ROSEMOUNT OIL LOSS RESPONSE TO NRC BULLETIN 9~-01, SUPPL. 01 1PA2386 7 1153GD Containment Pressure Wide ~nge YES 1.F NO ACTION REQUIRED. CONTINUE ENHANCED MONITORING ONLY. Although transmitter was*

manufactured before July 11, 1989, transmitter has a normal operating pressure <500 psi. NRC 90-0 I Suppl.

0 I has concluded that transmitters at low operating pressures achieve a high functional reliability and may be excluded from enhanced surveillance program.*

Additionally, previous calibration trending data (taken every refueling cycle) has indicated that this transmitter

  • has been a good performer with no signs of degradation due to oil-l_oss. Therefore, transmitter does not need to be replaced or enhanced monitoring performed.

However. PSE&G will continue to monitor the transmitter in order to maintain a high degree of confidence for detecting failure due to loss of fill-oil.

IPA2405 7 ll53GD Containment Pressure YES 1.F See same justification for IPA2386.

Wide Range IPT948A 6 1153HD Containment Pressure YES l.F See samejustification for 1PA2386.

Narrow Range 1PT948B 6 1153HD Containment Pressure YES 1.F See same justification for IPA2386.

Narrow Range IPT948C 6 Il53HD Containment Pressu~e YES l.F See same justification for IPA2386.

Narrow Range 1PT948D 6 1153HD Containment Pressure YES 1.F See same justification for IPA2386 ..

Narrow Range 1FT946 *6 1153HD Residual Heat Removal YES l.F See same justification for 1PA2386.

Pump SI Flow 1FT947 6 ll53HD Residual Heat Removal YES 1.F See same justification for IPA2386.

Pump SI Flow 1FT956 4 1153HD Residual Heat Removal YES 1.F

  • See same justification for 1PA2386.

Pump SI Flow IFT957 4 II53HD Residual Heat Removal . YES l.F See same justification for IPA2386.

Pump SI Flow

.IFT641A 4 1153HD Residual Heat Removal YES LF See same justification for IPA2386 .

Pump Recirc. Flow 6

~-----------------*--- _____ :___ _ _ _ _ _ _ _ _ _ , --------

ATTACHMENT 1 SALEM UNIT 1 ROSEMOUNT OIL LOSS RESPONSE TO NRC BULLETIN 90-01, SUPPL. 01 1Ff641B 1Ff640 4

4 ll53HD 1153HD Residual Heat Removal Pump Recirc. Flow Residual Heat Removal Pump Heat Exchanger

  • YES YES 1.F 1.F See same justification for 1PA2386.

See same justification for IP A2386.

Flow 1Ffl34 5 1153HD Low Pressure Letdown YES l.F See same justification for IP!\2386.

Flow 1FA3I60Zl 5 1153HD Containment Fan Coil YES l.F See same justification for lPA2386.

Unit Inlet Flow 1FA3165Zl 5 1153HD Containment Fan Coil YES l.F See same justification for IPA2386.

Unit Inlet Flow 1FA3169Zl 5 1153HD Containment Fan Coil

  • YES l.F See same justification for IPA2386.

Unit Inlet Flow 1FA3172Zl 5 1153HD. Containment Fan Coil YES l.F See same justification for lPA2386.

Unit Inlet Flow IFA3176Zl 5 1153HD Containment Fan Coil YES LF See same justification for IPA2386.

Unit Inlet Flow 1FA3539Zl 5 1153HD Containment Fan Coil YES l.F See samej'ustification for IPA2386.

Unit Outlet Flow 1FA3540ZI 5 1153HD Containment Fan Coil YES 1.F See same justification for IP A2386.

Unit Outlet Flow 1FA354IZI 5 ll53HD Containment Fan Coil YES 1.F See same justification for IPA2386.

Unit Outlet Flow 1FA3542ZI 5 U53HD Containment Fan Coil YES l.F See same justification for IPA2386.

Unit Outlet Flow 1FA3543ZI 5 1153HD Containment Fan Coil YES l.F See same justification for IPA2386.

Unit Outlet Flow 1Ff930 4 1153HD Containment Spray YES 1.F See same justification for IPA2386.

Additive Tank Outlet Flow 7

ATTACHMENT 1 SALEM UNIT 1 ROSEMOUNT OIL LOSS RESPONSE TO NRC BULLETIN 90-01, SUPPL. 01 lLT1649 5 l 153HA Pressurizer Level (Hot Shutdown)

NO NO NO ACTION REQUIRED. Transmitter is NON-IE category and provides indication only to the Hot Shutdown Panel. Transmitter is only categorized as safety-related since it needs to maintain RCS pressure boundary.

1Ff917 5 ll53HD Charging Pump YES 1.B NO ACTION REQUIRED. CONTINUE ENHANCED Discharge Flow MONITORING ONLY. Transmitter only provides indication of charging pump flow to control room operators during Safety Injection phase. The transmitter does not provide any input to RPS. ESFAS, or ATWS svstems used for automatic actuation.

Transmitter normal operating pressure is > 1500 psi and has reached maturity by exceeding Rosemount osi-month criteria of>60.000 psi-month. Transmitter is in the enhanced monitoring program and trending of calibration data (as-found/ as-left data) indicates that the transmitter has shown no signs of degradation due to oil-loss. The fact that the transmitter has reached it's psi-month criteria indicates that a high degree of reliability exists for this transmitter. This transmitter does not need to be replaced and continued enhanced monitoring of the transmitter on a refueling cycle interval basis is justified due to the demonstrated performance of the transmitter by our enhanced monitoring program, transmitter maturity and it's specific safety related function. Therefore, transmitter can be left installed for it's continued operating life, augmented bv enhanced montioring.

8

ATTACHMENT 1 SALEM UNIT 1 ROSEMOUNT OIL LOSS RESPONSE TO NRC BULLETIN 90-01, SUPPL. 01 1Ffl28 5 l 153HD Charging Flow Control YES l.B NO ACTION REQUIRED. CONTINUE ENHANCED MONTIORING ONLY. Transmitter provides indication of charging flow from either the reciprocating or C/SI charging pump. This transmitter provides iitdication to control room operators, as well as input to Pressurizer Level controller used during

  • normal plant operation. The transmitter does not provide any input to RPS. ESFAS. or ATWS systems used for automatic actuation. Transmitter normal operating pressure is >l 500 psi and has reached maturity by exceeding Rosemount psi-month criteria of

>60.000 osi-month. Transmitter is in the enhanced monitoring program and trending of calibration data *

(as-found/ as-left data) indicates that the transmitter has shown no signs of degradation due to oil-loss. The fact that the transmitter has reached it's psi-month criteria

  • indicates that a high degree of reliability exists for this transmitter. ~s transmitter does not need to be replaced and continued enhanced monitoring of the transmitter on a refueling cycle interval basis is justified due to the demonstrated performance of the ~

transmitter by our enhanced monitoring program, W transmitter maturity, and it's specific safety related function.* Therefore, transmitter can be left installed for

.it's continued_ operating life, augmented by enhanced montioring.

9 I\

ATTACHMENT 1

  • SALEM UNIT 1 ROSEMOUNT OIL LOSS RESPONSE
  • TO NRC. BULLETIN 90-01, SUPPL. 01

~-**-**t-1PT942 9 l 153GD Boron Injection Tank Discharge Pressure YES l.B NO ACTION REOUIRED, CONTINUE ENHANCED MONITORING ONLY. Transmitter only provides indicati.on and alarm of Boron htjection Tanlc (BIT) discharge pressure. The transmitter does not provide any input to RPS, ESFAS; or ATWS systems used for automatic actuation. Transmitter normal operating pressure is > 1500 psi and has reached maturity by exceeding Rosemount psi-month criteria of>60,000 psi-month. Failure of the transmitter will not degrade or prevent the automatic actuation of the SI system.

The basis for this is that adequate process protection is provided, such that, the design pressure of the C/SI

.charging system is conservatively greater than the maximum pump discharge pressure, which corresponds to the C/SI pump shutoff head plus the maximum RWST water level. Therefore, based on transmitter function, SI system design, and the performance and health of the transmitter having been so demonstrated,*

it is concluded that it can be left in service up to it's full ooerating lifeti.me.

IPT516A 9 l l53GD Steam Generator Steam YES 1.E NO ACTION REOUIRED. CONTINUE ENHANCED Dump To Atmosphere MONITORING ONLY. Transmitter provides steam generator pressure indication and input to MS 10 relief valve controller. The transmitter does not provide any input to RPS. ESFAS, or ATWS svstems used for automatie actuation. Transmitter normal operating pressure is between 500 and 1500 psi and has reached maturity by exceeding Rosemount psi-month criteria of

>60,000 psi-month. This transmitter does not need to be replaced and continued enhanced monitoring of the transmitter on a refueling cycle interval basis is justified due to the operating pressure range, transmitter maturity, and it's specific safety related function. Therefore, transmitter can be left htstalled for it's continued operating life, augmented by enhanced montioring. (Utilizes Noise Analysis) 10

ATTACHMENT 1 SALEM UNIT I-ROSEMOUNT OIL LOSS RESPONSE TO NRC BULLETIN 90-01, ~UPPL. 01 1PT526A 1PT536A 9

9 ll53GD 1153GD Steam Generator Steam Dump To Atmosphere Steam Generator Steam Dump To Atmosnhere YES YES l.E l.E See same required action for IPT516A.

(Utilizes Noise Analysis)

See same required action for 1PT516A.

(Utilizes Noise Analvsis) * ..

1PT546A 9 1153GD Steam Generator Steam YES . LE See same required action for 1PT516A.

Dump To Atmosnhere . (Utilizes Noise Analysis) 1PT919 9 1153GD .Safety Injection Pump YES l.E NO ACTION REQUIRED. CONTINUE ENHANCED Discharge Pressure , MONITORING ONLY. Transmitter provides indication orily for safety injection pump discharge pressure. The transmitter does not provide any input to RPS. ESFAS. or ATWS svstems used for automatic actuation. Transmitter normal operating pressure is between 500 *and 1500 psi and has reached maturity by exceeding Rosemount osi-month criteria of >60,000

  • psi-month. This transmitter does not need to be replaced and continued enhanced monitoring of the transmitter on a refueling cycle interval basis is justified due to the operating pressure range, transmitter maturity, and it's specific safety related 1PT923 9 l 153GD Safety IDjection Pump YES LE function. Therefore, transmitter can be left installed for

. it's continued operating life, augmented by enhanced montioring.

See same required action for 1PT919.

e.

Discharge Pressure 1PT505 .8 l 153GD 1st Stage Turbine YES l.C REPLACEMENT REQUIRED FOR TRANSMITTER Pressure Transmitter provides input and permissives to RPS and ATWS actuation svstems. Transmitter normal operating pressure is between 500 and 1500 psi and has not reached it's maturity. Therefore, this transmitter

  • will be scheduled for replacement at the earliest forced outage or refueling outage, which ever comes first.

1PT506 8 l 153GD lst Stage Turbine .

  • YES l.C See same required action for IPT505.

Pressure 11

ATTACHMENT 1 SALEM UNIT 1 ROSEMOUNT OIL LOSS RESPONSE TO NRC BULLETIN_ 90,.01, SUPPL. 01 1PT936A 8 l 153GD Accumulator Pressure .YES LE . NO ACTION REQUIRED. CONTINUE ENHANCED MONITORING ONLY. Transmitter only provides indication and alarm for accumulator pressure. The transmitter does not provide any input to RPS. ESFAS.

or ATWS . svstems used for automatic actuation.

Transmitter normal operating pressure is between 500 and 1500 psi and has reached maturity by exceeding Rosemount osi-monih criteria of>60,000 psi-month._

There are two channels per accumulator for indication of pressure, silch that redundancy exists. This transmitter does not need_ to be replaced and continued enhanced monitoring of the transmitter on a refueling cycle inter\rat basis is justified due to the operating pressure range, transmitter' maturity, and existing redundancy. Therefore, transmitter can: be left installed

-for it's continued operating life, augmented by enhanced monitoring.

lPT936B 8

  • 1153GD Accumulator Pressure YES LE See same reauired action for 1PT936A.

1PT936C 8 1153GD Accumulator Pressure YES LE See same reauired action for 1PT936A.

IPT9360 8 1153GD Accumulator Pressure YES LE See same reauired action for 1PT936A.

1PT937A 8 1153GD Accumulator Pressure YES* LE See same reauired action for IPT936A.

1PT937B 8 1153GD Accumulator Pressure

  • YES LE See same reatiired action for 1PT936A.

IPT937C 8 1153GD Accumulator Pressure YES LE See same reauired action for IPT936A.

1PT937D 8 1153GD Accumulator Pressure YES LE See same required action for IPT936A.

12

ATTACHMENT 1

. ,. I SALEM UNIT l'ROSEMOUNT OIL LOSS RESPONSE TO NRC BULLETIN 90-01, SUPPL. 01

. I

SUMMARY

OF ROSEMOUNT 1153 AND 1154 TRANSMITfER OIL LOSS EVALUATION Number of transmitters that are EXEMPT from NRC Bulletin 90-01, Suppl. 01 (>500000 Serial No.) = 66 Number of transmitters that are EXEMPT from NRC Bulletin 90-01, Suppl. 01 (NON SAFETY-RELATED) = 4 Number of transmitters that fall into NRC Bulletin 90-0.1, Suppl. 01 and require NO ACTION = 54

  • Number of transmitters that fall into NRC Bulletin 90-01, Suppl. QI and require REPLACEMENT = 2 TOTAL= 126

,1.,.

ATTACHMENT 2 SALEM UNIT 2 ROSEMOUNT OIL LOSS RESPONSE ~

TO NRC BULLETIN 90-01, SUPPL. 01 2LT459 5 ll54HH Pressurizer Level YES NO NO ACTION REOUIRED. Transmitter was manufactured after July 11, 1989. This was coDfirmed by verifying installed transmitter's serial number being greater than 500000. Therefore, transmitter does not fall into NRC Bulletin 90-01, Suool. 01 criteria.

2LT460 2LT461 2PT455 2PT456 2PT457 2PT474 5

5 9

9 9

9 1154HH 1154HH 1154SH 1154SH 1154SH 1154SH Pressurizer Level Pressurizer Level Pressurizer Pressure Pressurizer Pressure Pressurizer Pressure Pressurizer Pressure YES YES YES YES YES

. YES NO NO NO NO NO NO See same justification for 2LT459.

See same justification for 2LT459.

See same justification for 2LT459.

See same justification for 2LT459.

See same justification for 2LT459.

See same justification for 2LT459 .

2FT512 5 1154HH Steam Generator Flow YES NO See same justification for 2LT459.

2FT513 5 1154HH Steam Generator Flow YES NO See same justification for 2LT459.

  • 2FT522 5 1154HH Steam Generator Flow YES NO See same justification for 2LT459.

2FT523 5 1154HH Steam Generator Flow YES NO See same justification for 2LT459.

2FT532 5 1154HH Steam Generator Flow YES NO See same justification for 2LT459.

2FT533 5 1154HH Steam Generator Flow YES *NO See same justification for 2LT459.

2FT542 5 1154HH Steam Generator Flow YES NO See same justification for 2LT459.

2FT543 5 1154HH Steam Generator Flow YES NO See same justification for 2LT459.

2LT517 4 . 1154HH Steam Generator YES NO See same justification for 2LT459.

Narrow Range Level 2LT518 4 1154HH Steam Generator YES NO See same justification for 2LT459.

Narrow Range Level 2LT519 4 1154HH Steam Generator YES NO See same justification for 2LT459.

Narrow Range Level 2LT527 4 1154HH Steam Generator YES NO See same justification for 2LT459.

Narrow Range Level 2LT528 4 1154HH Steam Generator YES NO See same justification for 2LT459.

Narrow Range Level .

2LT529 4 1154HH Steam Generator YES NO See same justification for 2LT459.

Narrow Range Level 2LT537 .4 1154HH Steam Generator YES NO See same justification for 2LT459.

Narrow Range Level 2LT538 4 1154HH Steam Generator YES NO See same justification for 2LT459.

Narrow Range Level 1

ATTACHMENT 2 SALEM UNIT 2 ROSEMOUNT OIL LOSS RESPONSE

. TO NRC BULLETIN 90-01, SUPPL. 01 2LT539 2LT547 4

4 1154llll 1154llll Steam Generator Narrow Range Level Steam Generator YES YES NO NO

, See same justification for 2LT459.

See same justification for 2LT459.

2LT548 2LT549 2LT935C 4

4 4

ll54llll 1154llll 1153HD Narrow Range Level Stearn Generator Narrow Range Level Steam Generator Narrow Range Level Accumulator Level YES YES YES NO NO NO See same justification. for 2LT459 ..

See same justification for 2LT459.

  • See same justification for 2LT459.

2LT16273 4 ll53HD RlIR Mid-Loop Level . YES NO See same justification for 2LT459.

2LT16274 4 1153HD RlIR Mid-Loop Level YES NO See sarnejustification for 2LT459.

2PT16272 5 1153GD RlIR Mid-Loop YES NO See *same justification for 2LT459.

Pressure

. 2PT16275 5 1153GD RHR. Mid-Loop YES NO See same justification for 2LT459.

Pressure*

2LT470 4 1153DD Pressurizer Relief Tank NO NO NO ACTION REQUIRED. Transmitter is used in a Level NON-SAFETY RELATED function. There,fore, this transmitter is exempt from the NRC Bulletin 90-01, Suppl. 01 criteria.

2LT1003 4 1153DD Reactor Coolant Drain NO *NO NO ACTION REQUIRED. Transmitter is µsed in a Tank Level NON-SAFETY RELATED fun,ction. Therefore, this transmitter is exempt from the NRC Bulletin 90-01,.

Suppl. O1 criteria.

  • 2FI'601A 4 1153HD RlIR Heat Exchanger YES NO See same justification for 2LT459.

Component Cooling Water OUtlet Flow 2

ATTACHMENT 2' SALEM UNIT 2 ROSEMOUNT OIL LOSS RESPONSE TO NRC BULLETIN 90.:.01, SUPPL. 01

lLT501 5 l 153HD Steam Generator Wide Range Level YES l.C - ACTION REQUIRED. TRANSMITTER IS ALREADY SCHEDULED TO BE REPLACED UPCOMING REFUELING OUTAGE. The transmitter was manufactured before July 11, 1989. PSE&G will 2LT502 5 1153HD Steam Generator Wide -YES l.C be relpacing this transmitter in the upcoming refueling outage (2R7), on or about March 20, 1993, with a transmitter (Rosemount Model l l 54HH for level/flow and l 154SH for pressure) that has been manufactured after July 11, 1989 (serial number >500000).

See same required action for 2LT50 I.

Range Level 2LT503 5 1153HD Steam Generator Wide YES l.C See same reqtJired action for 2LTSO I.

Range Level 2LT504 5 1153HD Steam Generator Wide -YES l.C See same required action for 2LT50 I.

Ran~Level 2PT514 9 1153GD Steam Generator YES. l.C See same required action for 2LT501.

Pressure 2PT515 9 1153GD Steam Generator YES l.C See same required action for 2LT50 I. .

Pressure 2PT516 9 1153GD Steam Generator YES 1_.c See same required action for 2LT50 I.

Pressure 2PT524 9 1153GD Steam Generator YES . l.C See same required action for 2LT50 I.

Pressure 2PT52,5 9 1153GD Steam Generator YES l.C See sam~ required action for 2LT50 I.

Pressure 2PT526 9 1153GD Steam Generator YES l.C See same required action for 2LT50 I.'

Pressure 2PT534 9 1153GD Steam Generator YES l.C See same required action for 2LT50 I.

Pressure 3

ATTACHMENT 2 SALEM UNIT 2 ROSEMOUNT OIL LOSS RESPONSE ~

TO NRC BULLETIN 90-01, SUPPL. 01 2PT535 2PTS36 9

9 ll53GD llS3GD Steam Generator Pressure Steam Generator Pressure YES YES LC LC See same required action for 2LTSOL See same required action for 2LTSO 1..

2PT544 9 l 1S3GD Steam Generator YES LC See same required action for 2LTSO 1.

Pressure 2PT545 9 ll53GD Steam Generator YES LC See same required action for 2LTSOL Pressure 2PT546 9 11S3GD Steam Generator YES LC See same required action for 2LTSO L Pressure 2PT403 9 llS3GD Reactor Coolant YES LA See same required action for 2LT50L Pressure 2PT405 9 1153GD Reactor Coolant YES LA See same required action for 2LT501.

Pressure 2Ff414 s 1153HD Reactor Coolant Flow YES LA See same required action for 2LT50 I. .

<Utilizes Noise Analvsis) 2Ff41S 5 11S3HD .. Reactor Coolant Flow YES I.A See.same renuired action for 2LT50 I.

2Ff416 5 11S3HD Reactor Coolant Flow YES LA See same required action for 2LTSO 1.

<Utilizes Noise Analvsis) 2Ff424 5 11S3HD Reactor Coolant Flow YES I.A See same reouired action for 2LTSO I.

2Ff42S s 1153HD Reactor Coolant Flow YES LA See same reouired action for 2LTSOI.

2Ff426 2Ff434 2Ff43S 2Ff436 2Ff444 5

5 5

5 5

11S3HD ll53HD 1153HD 1153HD 1153HD Reactor Coolant Flow Reactor Coolant Flow Reactor Coolant Flow Reactor Coolant Flow Reactor Coolant Flow YES YES YES YES YES LA LA LA LA LA See same renuired action for 2LT50 I.

See same reouired action for 2LT501.

See same required action for 2LT501.

<Utilizes Noise Analvsis)

See same renuired action for 2LT501.

See same reQuired action for 2LT501.

2Ff445 .5 11S3HD Reactor Coolant Flow YES LA See same renuired action for 2LT50L 2Ff446 5 1153HD Reactor Coolant Flow YES LA See same reauired action for 2LTSO 1.

4

ATTACHMENT 2 '

SALEM UNIT 2 ROSEMOUNT OIL LOSS RESPONSE TO NRC BULLETIN 90-01, SUPPL~ 01 2LT934A 4 l 153HD Accumulator Leve.I YES 1.E NO ACTION REQUIRED. CONTINUE ENHANCED MONITORING ONLY. Although transmitter was manufactured before July 11, 1989, transmitter has reached it's PSI-MONTH criteria of>60.000 psi-month

(> 130,000 psi-month where noted) with a normal

  • c;>perating pressure within the boundaries of >500 psi and <1500 psi. The maturity of the transmitter indicates that the transmitter will achieve a high functional reliability. Additionally, previous trending data (taken every refueling outage) has assilred PSE&G that the transmitter has been a good performer and supports Rosemount and NUMARC's conculsion on transmitter health/performance as it relates to psi-month criteria. Therefore, transmitter does not need to be replaced or enhanced monitoring performed.

However. PSE&G will continue to monitor the transmitter in order to maintain a high degree of confidence for detecting failure due to loss of fill-oil.

2LT934B .4 1153HD Accumulator Level YES 1.E See same justification for 2LT934A.

2LT934C '4 1153HD Accumulator Level YES 1.E See same justification for 2LT934A.

  • 2LT934D 4 1153HD Accumulator Level YES 1.E See same justification for 2LT934A.

2LT935A 4 1153HD Accumulator Level YES 1.E See same justification for 2LT934A.

2LT935B 4 1153HD Accumulator Level YES 1.E . See same justification for 2LT934A.

2LT935D 4 1153HD Accumwator Level YES 1.E See same! juitification for 2LT934A.

2FT918 6 1153HD Safety Injection Pump YES l.E See same juStification for 2LT934A.

Discharge Flow (Meets > 130,000 osi-month criteria by Rosemount) 2FT922 6 1153HD Safety lrtjection Pump YES 1.E See same justification for 2LT934A.

Dischar~e Flow (Meets >130,000 psi-month criteria by Rosemount) 2FA1087 5 ' 1153HD Auxiliary Feedwater YES 1.E See same justification for 2LT934A.

Flow 5

ATTACHMENT 2 SALEM UNIT 2 ROSEMOUNT OIL LOSS RESPONSE TO NRC BULLETIN 90-01, SUPPL. 01 2FA1091 2FA1095 5

5 1153HD 1153HD Auxiliary Feedwater Flow Auxiliary Feedwater .

YES YES 1.E 1.E See same justification for 2LT934A.

__See same justification for 2LT934A.

Flow.

2FA1097 5 1153HD Auxiliary Feedwater YES 1.E See same justification for 2LT934A.

Flow 2PA2386 7 1153GD Containment Pressure *YES 1.F NO ACTION REQUIRED. CONTINUE ENHANCED Wide Range MONITORING ONLY. Although transmitter was manufactured before July 11, 1989, transmitter has a normal operating pressure <500 psi. NRC 90-01 Suppl.

O1 has concluded that transmitters at low* operating pressures achieve a high functional* reliability and may be excluded from enhanced surveillance program.

, Additionally, previous trending data (taken every refueling cycle) has indicated that this transmitter has been a good performer with no signs of degradation due to oil-loss. Therefore, transmitter does not need to be replaced or enhanced monitoring perfonned. However.

PSE&G will continue to monitor the transmitter in order to maintain a high degree of confidence for 2PA2405 2PT948A 7

6 1153GD Containment Pressure Wide Range 1153HD Containment Pressure YES YES 1.F 1.F detectin2 failure due to loss of fill-oil.

See same justification for 2PA2386.

See same justification for 2PA2386~

Narrow Range 2PT948B 6 1153HD Containment Pressure YES 1.F See same justification for 2PA2386.

Narrow Range

'2PT948C 6 1153HD Containment Pressure YES 1.F See same justification for 2PA2386.

Narrow Range 2PT948D 6 1153HD Containment Pressure YES 1.F See same justification for 2PA2386.

Narrow Range 2LT960 5 1153HD

  • Reactor Water Storage YES l.F See samejustifieation for 2PA2386.

Tank Level 6

ATTACHMENT 2 .,

SALEM UNIT 2 ROSEMOUNT OIL LOSS RESPONSE TO NRC BULLETIN 90-01, SUPPL. 01 2LT961 2~T962 5

5, 1153HD 1153HD Reactor Water Storage Tanlc Level Reactor Water Storage Tanlc Level YES YES 1.F l.F See same justification for 2PA2386.

See same juStification for 2PA2386.

2LT963

  • 5 1153HD Reactor Water Storage YES l.F See same justification for 2PA2386.

TanlcLevel 2Ff946" 6 1153HD Residual Heat Removal YES 1.F See same justification for 2PA2386.

Pump SI Flow 2Ff947 6 1153HD Residual Heat Removal YES 1.F See same justification for 2PA2386.

Pump SI Flow 2Ff956 4 1153HD Residual Heat Removal YES 1.F See same justification for 2PA2386.

Pump SI Flow 2Ff957 4 1153HD Residual Heat Removal YES 1.F See same justification for 2PA2386.

Pumi> SI Flow 2Ff641A 4 1153HD Residual Heat Removal YES l.F See same justification for 2PA2386.

Pumo Recirc. Flow 2Ff641B 4 ll53HD Residual Heat Removal YES 1.F See same justification for 2PA2386.

Pump Recirc. Flow 2Ff640 4 1153HD Residual Heat Removal YES 1.F See same justification for 2PA.2386.

Pump Heat Exchanger

'Flow 2Ff134 5 1153HD Low Pressure Letdo'wn YES 1.F See same justification for 2PA2386.

Flow 2FA3160Zl 5 .ll53HD Containment Fan Coil YES 1.F See same justification for 2PA2386.

Unit Inlet Flow 2FA3165Zl 5 1153HD Containment Fan Coil YES 1.F See same jmtification for 2PA2386.

Unit Inlet Flow 2FA3169Zl 5 1153HD Containment Fan Coil YES 1.F See same justification for 2PA2386.

Unit Inlet Flow 2FA3172Zl 5 1153HD Containment Fan Coil YES 1.F See same justification. for 2PA2386; Unit Inlet Flow 2FA3176Zl 5 1153HD Containment Fan Coil YES 1.F See same justification for 2PA2386.

Unit Inlet Flow 7

ATTACHMENT 2 SALEM UNIT 2 ROSEMOUNT OIL LOSS,RESPONSE TO NRC BULLETIN 90-01, SUPPL. 01 2FA3539Zl 2FA3540Zl 5

5 1153HD 1153HD Containment Fan Coil Unit Outlet Flow Containment Fan Coil Unit Outlet Flow YES YES 1.F l.F See same justification for 2PA2386.

See same justification for 2PA2386.*

2FA3541Zl 5 ll53HD Containment Fan Coil YES l.F See same justification for 2PA2386.

Unit Outlet Flow 2FA3542Zl 5 1153HD Containment Fan Coil YES 1.F See same justification for 2PA2386.

Unit Outlet Flow 2FA3543Zl 5 1153HD Containment Fan Coil YES 1.F See same justification for 2PA2386.

Unit Outlet Flow 2Ff930 4 1153HD Containment Spray YES 1.F See same justification for 2P A2386.

Additive Tank Outlet Flow 2LT1649 5 1153HA *Pressurizer Level NO NO NO ACTION REQUIRED. Transmitter is NON-IE (Hot Shutdown) category and provides indication only to the Hot Shutdown Panel. Transmitter is only categorized as safety-related since it needs to maintain RCS pressure boundary.

2LT1640 4 l 153HD Steam Generator NO NO See same justification for 2LT1649.

Narrow Range Level

<Hot Shutdown) 8

ATTACHMENT 2 SALEM UNIT 2 ROSEMOUNT OIL LOSS RESPONSE TO NRC BULLETIN 90-01, SUPPL. 01 2Ff917 5 l 153HD Charging Pump Discharge Flow YES l.B NO ACTION REQUIRED. CONTINUE ENHANCED MONITORING ONLY. Transmitter only provides indication of charging pump flow to control room operators during Safefy Injection phase. The transmitter does not provide any input to RPS. ESFAS.

or ATWS systems used for automatic actuation.

Transmitter normal operating pressure is > 1500 psi and has reached maturity by exceeding Rosemount psi-month criteria of>60.000 psi-month. Transmitter is in the enhanced monitoring program and trending of calibration data (as-found/ as-left data) indicates that the transmitter has shown no signs of degradation due to oil-loss. The fact that the transmitter has reached it's psi-month criteria indicates that a high degree of reliability exists for this tranmsitter. This transmitter does not need to be replaced and continued enhanced monitoring of the transmitter on a refueling cycle interval basis is justified due to the demonstrated performance of the transmitter by our enhanced rnonitonng program, transmitter maturity, and it's specific safety related function. Therefore, transmitter can be left installed for it's continued operating life, amm1ented by enhanced monitoring.

9

ATTACHMENT 2 SALEM UNIT 2 ROSEMOUNT OIL LOSS RESPONSE TO NRC BULLETIN 90-01, SUPPL. 01 2FT128 5 l 153HD Charging Flow Control YES 1.B NO ACTION REQUIRED. CONTINUE ENHANCED .

MONITORING ONLY. -Transmitter provides indication of charging flow from either the*

reciprocating or C/SI charging pump. This transmitter provides indication to control room operators, as well as input to Pressurizer Level controller used during normal plant operation. The transmitter does not provide any input to RPS, ESFAS. or ATWS systems used for automatic actuation. Transmitter normal operating pressure is > 1500 psi and has reached maturity by exceeding Rosemount psi-month criteria of

>60,000 psi-month. Transmitter is in the enhanced montoring program and trending of calibration data*

(as-found/ as-left data) indicates that the transmitter has shown no sigtis of degradation due to oil-loss. The fact that the transmitter has reached it's psi-month criteria indicates that a high degree of reliability exists for this*

tranmsitter. This transmitter does not need to be replaced and continued enhanced monitoring of the transmitter on a refueling cycle interval basis is justified due to the demonstrated performance of the

.transmitter by our enhanced monitoring program.

transmitter maturity, and it's specific safety related function. Therefore, transmitter can be left installed for it's continued operating life, augmented by enhanced monitorin~.'

10

ATTACHMENT 2 SALEM UNIT 2 ROSEMOUNT OIL LOSS RESPONSE TO NRC BULLETIN 90-01, SUPPL. 01 2PT936A 8 l 153GD Accumulator Pressure YES 1.E NO ACTION REQUIRED, CONTINUE ENHANCED MONITORING ONLY. Transmitter only provides indication and alarm for* accumulator pressure. The transmitter does not provide any input to RPS. ESFAS.

or ATWS svstems used for automatic actuation.

Transmitter normal operating pressure is between 500

  • and 1500 psi and has reached maturity by exceeding Rosemount psi-month criteria of >60,000 psi-month.

There are two channels per accumulator for indication of pressure, such that redundancy exists. This transinitter does not need to be replaced and continued enhanced monitoring of the transmitter on a refueling cycle interval basis is justified due to the operating pressure range, transmitter maturity, and existing redundancy. Therefore, transmitter can be left installed for it's continued operating life, augmented by enhanced monitoring.

2PT936B 8 1153GD Accumulator Pressure YES 1.E See same required action for 2LT936A.

2PT936C 8 1153GD Accumulator Pressure YES 1.E. See same reouired action for 2LT936A.

2PT936D 8 1153GD Accumulator Pressure YES l.E See same required action for 2LT936A.

2PT937A 8 1153GD Accumulator Pressure YES 1.E See same required action for 2LT936A.

2PT937B 8 1153GD Accumulator Pressure YES l.E See same required action for 2LT936A.

2PT937C 2PT937D 8

8 1153GD 1153GD Accumulator Pressure Accumulator Pressure YES YES 1.E l.E See same reauired action for 2LT936A.

See same re<1uired action for 2LT936A. I 11

ATTACHMENT 2 SALEM UNIT .2 ROSEMOUNT OIL LOSS RESPONSE TO NRC BULLETIN 90-01, SUPPL. 01

_2PT942 9 1153GD Boron Injection Taruc Discharge Pressure YES l.B NO ACTION REQUIRED. CONTINUE ENHANCED MONITORING ONLY. Transmitter only provides indication and alarm of Boron Injection Tank (BIT) discharge pressure. The transmitter does not provide any input to RPS. ESF AS. or ATWS systems used for automatic actuation. Transmitter normal operating pressure is> 1500 psi and has reached maturity by exceeding Rosemount psi-month criteria of>60,000 psi-month. Failure of the transmitter will not degrade or prevent the automatic actuation of the SI system.

The basis for this is that adequate process protection is provided, such that, the design pressure of the C/SI charging system is conservatively greater than the maximum pump discharge pressure, which corresponds to the C/SI pump shutoff head plus the maximum RWST water level. Therefore, based on transmitter function. SI system design, and the performance and health of the transmitter having been so demonstrated; it is concluded that it can be left in service up to it's full operating lifetime.

I 12

~-

ATTACHMENT 2 SALEM UNIT 2 ROSEMOUNT OIL LOSS RESPONSE TO NRC BULLETIN 90-01, SUPPL. 01 2PT516A 9 l 153GD Steam Generator Steam Dump To Atmosphere YES l .E NO ACTION REQUIRED. CONTINUE ENHANCED MONITORING ONLY. Transmitter provides steam generator pressu.re indication and input to MSlO relief valve controller. The transmitter d0es not provide any input to RPS. ESFAS. or ATWS svstems used for automatic actuation. Transmitter normal operating pressure is between 500 and 1500 psi and has reached maturity by exceeding Rosemount psi-month criteria of

>60,000 psi-month. This transmitter does not need to be replaced and continued enhanced monitoring of the transmitter on a refueling cycle interval basis is justified due to the operating pressure range, transmitter maturity, and it's specific safety related

. function. Therefore, transmitter can be left installed for it's continued operating life, augmented by enhanced montioring. (Utilizes Noise Analysis) 2PT526A 9 1153GD Steam Generator Steam YES l.E See same required action for 2PT516A.

Dump To Atmosphere 2PT536A 9 1153GD Steam Generator Steam YES l.E See same required action for 2PT516A.

Dump To Atmosphere 2PT546A. 9 1153GD Steam Generator Steam *YES l.E See same required action for 2PT516A.

Dump To Atmosphere I

13

ATTACHMENT 2 SALEM UNIT 2 ROSEMOUNT OIL LOSS RESPONSE

-TO NRC BULLETIN 90-01, SUPPL. 01 2PT919 9 1153GD Safety Injection Pump Discharge Pressure YES l.E NO ACTIONREOUIRED. CONTINUE ENHANCED MONITORING ONLY. Transmitter provides indication only for safety injection pump discharge pressure. The transmitter does not provide any input to RPS. ESFAS. or ATWS systems used for automatic actuation. Transmitter normal operating pressure is between 500 and 1500 psi and has reached maturity by exceeding Rosemount psi-month criteria of>60,000 psi-month. *This transmitter does not need to be

  • replaced and continued enhanced monitoring of the
  • transmitter on a refueling cycle interval basis is justified due to the operating pressure range, transmitter maturify, and it's specific safety related function. Therefore, transmitter can be left installed for it's continued operating life, augmented by enhanced montioring.

2PT923 9 1153GD Safety Injection Pump YES 1.E See same required action for 2PT919.

Dischar~e Pressure 2PT505 9 1153GD 1st Stage Turbine YES l.C REPLACEMENT REQUIRED FOR TRANSMITIER Pressure Transmitter provides input and oermissives to RPS and ATWS actuation systems. Transmitter normal operating pressure is between 500 and 1500 psi and has not reached it's maturitv. Therefore, this transmitter will be scheduled for replacement at the earliest forced outage or refuelin~ outa~e; which ever comes first.

2PT506 *8 1153GD 1st Stage Turbine.

  • YES l.C See samt! required action for 2PT505.

Pressure 14

ATTACHMENT 2 SALEM UNIT 2 ROSEMOUNT OIL LOSS RESPONSE TO NRC BULLETIN 90-01, SUPPL. 01

SUMMARY

OF ROSEMOUNT 1153 AND 1154 TRANSMITIER OIL LOSS EVALUATION Number of transmitters that are EXEMPT from NRC Bulletin 90-01, Suppl. 01 (>500000 Serial Number)

Number of transmitters that are EXEMPT from NRC Bulletin 90-01, Suppl. 01 (NON SAFETY-RELATED)

Number of transmitters that fall into NRC Bulletin 90-01, Suppl. 01 and require NO ACTION Number of transmitters that fall into NRC Bulletin 90-01, Suppl. 01 and previously scheduled for REPLACEMENT Number of transmitters that fall into NRC Bulletin 90-01, Suppl. 01 and require REPLACEMENT

= 33

= 4

= 59

= 30

= 2 TOTAL = 128 15

Reference:

NIR-N93032

  • RE.ViEJq OF REXJJ&iw ACrIOOS In response-to NRc Infonnation Notice 89-42, the original Bulletin 90-01, arx1 aw~icable Rosemount Technical Bulletins, Hope Creek has previously identified all Rosemount Mcxlel 1153, Series B transmitters in sei:vice arx1 inplenelte:i an enhanced sw:veillance program for each transmitter. . Hope Creek does not use Rosem:Junt Model 1153, Series D, or Model 1154 transmitters. BaSed upon specific actions requested in the Bulletin SUpplenelt, a detailed review of the installed -transmitters was perfonned with transmitters categorized by safety function, rionnal operating pre5sure rarges, am. psi-m::mth criteria.

'!he results of this review, follO!Ning the outline of the Requeste:i Actions of the Bulletin SUpplenelt, are presente:i in the EVAIIJATION OF ~ AC'I'IONS section belOIN.

Additionally, the Hope Creek warehouse Rosenn.mt invento:cy was :reviewed for bulletin applicability, am all. transmitters identified for repair or replacement actions have been placed on HOID" arx1 have had "NONCDNFORMANCE" tags affixed to them. A listirg of these transmitters has been prm7ided to the station for prioritization of the corrective actions required for each transmitter identified.

E.'VAII1ATIW OF REXDESl'E1> ACI'IOOS

1. '!he total population of Rosemount Model 1153, Series B transmitters installed at Hope Creek is 267 ,* of which 264 are used in safety-relate:i systems or A'IWs applications. Of those 264, a total of 82 Model 1153 transmitters that had been manufactured before July 11, 1989 have been previously replaced with units manufactured after that date.
  • o.it of the 182 remainirg transmitters marnrractured before July 11, 1989, 101 are used in lO!N pressure awlicatlon.s am 42 have surpassed their psi-nv:mth threshold. * 'Ibis leaves 39 transmitters for which the provisions of items l(c) am l(d) awly as detailed belOIN.

1(a) RPS, F.'SF2\S. am M"5 Transmi.~ > 1500 psi

'Ibis eatego:cy is not awlicable; there are no transmitters

  • in use at Hope Creek with nonnal operating pressures > 1500 psi.

1(b) other Safety-Related Iq:.plicatiais > 1500 psi

  • 'Ibis catego:cy is also not awlicable; there are no transmitters in use at Hope Creek with nonnal operatirg pressures > 1500 psi.

1(c) RPS, ~. ani MH> Transmitters> 500 psi 5 1500 psi, (psi-nart:h threshold not inet) . .

  • A total of 29 transmitters were identified which fell into this catego:cy.~

None of these 29 are used. in RPS or A'IWS Reactor Pressure Vessel pressu+e or water level applications. 21 of these transmitters have been identified for replacement no later than the errl of the next refueling outage (scheduled for 4/22/94) am 2 of the 21 were already replaced on 2/17/93. 'lhese transmitters are listed in Attadnrent 1. '!he remaining 8 transmitters are justified for use with enhanced natltori.rig am are listed in Attadllrent 2 .with summacy justifipations.

  • 1 (d) Other Safety-Related AR>licatims > 500 psi. 5 1500 psi, (psi-nart:h threshold not met) . .

'!here are a total of 10 transmitters that fall into this category. .All of these transmitters will continue to be 100nitored a:t least once per 23 nonths using an enhanced sm:veillance 100nitoring program. 'lhese transmitters are listed in Attadllrent 3. .

1(e) Hen-RPS, ~. ani MH> Trimsmitters > soO psi 5 1500 psi, (psi-DD'Ith threshold met) I arll .

1(f) 'Art:/ Safety-Related Transmitters 5 500 psi Hope Creek interrjg to. continUe an enhanced surveillance inOnitoring program for all safety related 1153 transmitters, but may m::xlify the content of i.ntividual transmitter programs based upon psi-iIK>nth, lOW' pressure sei:vice, manufacturing date am system application. At a

m:i.ninrum, transmitters will be checked for sluggish response during minllnum calibration inteJ:vals of 23 nonths. .
2. EnharDed SUrveillaI"De Prw;c;am

'!he 9nbancea sm:veillance program for the transmitters that are part ~f this evaluation follows the calibration data trerrlin:]*recarmnerrlations presented by RosenD1.mt in their piblished "Technical Bulletins". '!his enhanced sm:veillance program, followi.ng manufacturer recamnerrlation, will provide the riecessary data . am the high degree of. confidence required. for. detection of degradation caused by loss of fill-oil. '!he enhanced 100nitori.ng program at Hope Creek station consists *of the follCMing:

  • Drift Monitori.ncJ All transmitter zero drift is trerned am analyzed in aexx>rdance with the RoseJoount Technical Bulletin guidelines.

-1

  • Transient Response Monitoring calibration of the transmitters includes observation of the transmitter for a sluggish transient :response.

'!he operating' staff perfo:nn.s channel checks ih accordance with Technical Specification requirenents. Deviation from channel to channel is noted arrl investigated. Degradation can be ItDnitored in this manner.

  • Process Noise Monitoring Transmitter process noise analysis is an available tool to IOC>nitor a questionable transmitter while it is in service. Procedures have been :i.Irplemented for selected transmitters to obtain spectnnn power density data, on a quarterly basis, for conparison against baseline data to check for degradation in response to pnx::ess noise. '!his program has been successful in enhancirg carcqxment reliability.

'Ihere have been no transmitter failures.due to oil loss that have resulted in failure of any protection system to perfo:im a safety function when called upon.

1. Hope Creek will take the actions requested.
2. With regard to the above actions:
a. '!he. actions that Hope Creek will complete to meet Item 1 of the Bulletin SUpplement's Requested Actions*are detailed in Attachments 1, 2, and 3 and. in the '.EVAIIJATION OF ~ ACTIONS Section of this Enclosure.

b.. '!he sdledule for completion of the Item 1 Requested Actions is also provided in Attachnents 1, 2 arrl 3 arrl in the EVAIIJATION OF ~

ACTIONS Section of this Enclosure.

c. PSE&G will cxnfinn, upon their campletion, that Iterri.s 1 arrl 2 of the Bulletin SUpplem:mt Required Actions have been canpleted.
3. Not applicable - PSE&G is taking no exception to the requested actions.

ATTACHMENT 1 NRC 90-01 SUP 1 ITEM l~C TRANSMITTERS TO BE REPLACED COMPONENT ID . CLASS DESCRIPTION 1ABPDT-N086A-B21 ESF STEAM LINE A FLOW - NSSSS 1ABPDT-N086C-B21 ESF STEAM LINE A FLOW - NS SSS 1ABPDT-N087A-B21 ESF STEAM LINE B FLOW - NSSSS 1ABPDT-N087B-B21 ESF STEAM LINE B FLOW - NS SSS 1ABPDT-N087C-B21 ESF STEAM LINE B FLOW - NSSSS 1ABPDT-N087D-B21 ESF STEAM LINE B FLOW - NS SSS 1ABPDT-N088A-B21 ESF , *sTEAM LINE C FLOW - NSSSS 1ABPDT-N088B-B21 1ABPDT-N088C-B21 1ABPDT-N089A-B21 ESF ESF ESF STEAM LINE C. FLOW - NSSSS STEAM LINE C FLOW - NSSSS STEAM LINE D FLOW NSSSS e

1ABPDT-N089C-B21 ESF STEAM LINE D FLOW - NSS.SS 1ABPDT-N089D-B21 ESF STEAM LINE D FLOW - NSSSS 1BBPT-5824A ESF REACTOR PRESS - MSIV SEAL SYST 1BBPT-N079D-B21 ESF REACT PRESS TO SRV LO LO SET LOGIC 1BBPT-N079H-B21 ESF REACT PRESS - SRV LO LO SET LOGIC 1BCPT-N058A-Ell ESF LPCI INJECT VLV HV-F017A Ell 1BCPT-N058B-Ell ESF LPCI INJECT VLV HV-F017B Ell 1BCPT--N058C-Ell ESF LPCI INJECT VLV HV-F017C Ell 1BCPT-N058D-Ell ESF LPCI INJECT VLV HV-F017D Ell 1FCPDT-N057B-E51 ESF RCIC STEAM LINE DIF PRESS 1FCPDT-N057D-E51 ESF RCIC STEAM LINE DIF PRESS Page 1

ATTACHMENT 2 NRC 90-01 SUP 1 ITEM 1.C TRANSMITTER EXCEPTIONS COMPONENT ID' CLASS DESCRIPTION

JUSTIFICATION: TRANSMITTER MEASURES MAIN STEAMLINE "D" PRESSURE BETWEEN INBOARD AND OUTBOARD MSIV'S; PROVIDES HIGH PRESSURE*

SAFETY INTERLOCK TRIP TO MSIV SEALING, SYSTEM INBOARD ISOLATION VALVE HV-5837A TO PREVENT STEAM BACKFLOW TO THE PRIMARY

  • A CONTAINMENT INSTRUMENT GAS SYSTEM, LOW W PRESSURE ALARM AND PRESSURE INDICATION TO .

THE CONTROL .ROOM. THE SAFETY INTERLOC!l{ .

CAN BE BYPASSED FROM THE CONTROL ROOM; A SERIES CHECK VALVE ALSO PREVENTS BACKFLOW; OPERATOR CAN ESTIMATE STEAM PRESSURE* FROM OTHER RELIABLE MAIN STEAM INSTRUMENTS; THEREFORE, THE TRANSMITTER FUN~ION lS NOT CRITICAL TO MSIVSS OPERATION AND FAILURE WOULD NOT PREVENT MSIVSS SAFETY FUNCTION.

LOSS OF FILL OIL WOULD RESULT IN SLUGGISH RESPONSE TO INCREASING PRESSURE AND SETPOINT DRIFT HIGH WHICH WOULO NOT PREVENT ISOLATION VALVE OPERATION. ,

TRANSMITTER PERFORMANCE HAS BEEN EXCELLENT WITH OIL LOSS LIFETIME PROJECTION OF 470 YEARS. ,

1BEPT-N090N-B21 ESF REAC PRESSURE FOR CS LOGIC A ENHANCED SURVEILLANCE PROGRAM: DAILY .

CHANNEL CHECK, QUARTERLY NOISE ANALYSIS, ~

18 MONTH CALIBRATION CHECK FOR SLUGGISH RESPONSE - RANGE CODE 9 DRIFT TRENDING NOT ACCURATE. JUSTIFICATION: TRANSMITTER FUNCTION IS TO PROVIDE LOW REACTOR PRESSURE PERMISSIVE FOR CORE SPRAY PUMP A INBOARD AND OUTBOARD VALVES F004 AND FOOS; 1 OUT OF 2, TAKEN TWICE LOGIC -OTHER CHANNELS ARE N090A., N090E AND N090J.

LOSS OF TRANSMITTER FILL OIL WOULD RESULT

. lN SLOW RESPONSE TO INCREASING PRESSURE

.AND SETPOINT DRIFT HIGH; NEITHER FAILURE Page 1

ATTACHMENT 2 NRC 90-01 SUP 1. ITEM l.C TRANSMITTER EXCEPTIONS .

. COMPONENT IO CLASS DESCRIPTION Attachment 1BEPT-N090N-B21 ESF MOOE WOULD.PREVENT FUNCTION OF CORE SPRAY PERMISSIVE DURING REACTOR DE-PRESSURIZATION - N090N PERMISSIVE WOULD OCCUR AT HIGHER PRESSURE. BUT N090E OR, N090A CAUSE SYSTEM PERMISSIVE AT CORRECT PRESSURE. TRANSMITTER PERFORMANCE IS SATISFACTORY BASED ON TWO CALIBRATIONS AND REPEATABLE NOISE SPECTRUM ANALYSES ' A PERFORMED QUARTERLY. ~

1BGFT-11479A ESF .CAVS FLOW TO RWCU DIFF FLOW ISOL ENHANCED SURVEILLANCE PROGRAM: DAILY

.CHANNEL CHECKS; 18 MONTH CALIBRATION DRIFT

  • TRENDING. JUSTIFICATION: 1BBFT-11479A'& B PROVIDE FLOW SIGNALS FOR CRACK ARREST VERIFICATION SYSTEM (CAVS) FLOW TO THE RWCU. DIFFERENTIAL FLOW LEAK DETECTION ISOLATION CHANNELS A AND D WHICH. ISOLA~E RWCU ON EXCESSIVE DELTA FLOW BETWEEN RWCU INLET AND OUTLET. THE CAVS FLOWS ARE 4 TO 5 GPM AND REPRESENT ONLY ABOUT lt OF THE TOTAL RWCU INLET FLOW DURING NORMAL OPERATION. LOSS OF FILL OIL WOULD RESULT IN MAXIMUM SIGNAL DRIFT OF 1.4 GPM AND SLUGGISH RESPONSE TO CHANGES IN CAVS FLOW.

SMALL TO MEDIUM RWCU PIPE LEAKS WOULD NOT

  • NORMALLY CAUSE CHANGES IN CAVS FLOW~ THE POSSIBLE 1.4 GPM ERROR IS WITHIN SETPOINT~

CALCULATION ERROR MARGINS. THE DELTA FLOWW SETPOINT IS 56.3 GPM WITH PROCESS LIMIT OF 100 GPM. THERE* ARE TWO DIVERSE RWCU ISOLATION SYSTEMS AS BACKUP TO EACH OF THE

  • TWO RWCU DIFF FLOW CHANNELS - HIGH ROOM TEMPERATURE AND DIFFERENTIAL TEMPERATURE.

THEREFORE, LOSS OF.FILL OIL IN EITHER CAVS TRANSMITTER WOULD NOT HAVE A SIGNIFICANT -

EFFECT ON RWCU LEAK DETECTION CAPABILITY OR PREVENT RWCU ISOLATION ~UNCTION DUE TO PIPE LEAKAGE. TRANSMITTER PERFORMANCE FOR EACH .CHANNEL IS SATISFACTORY BASED ON ONE Page,2

ATTACHMENT 2 NRC 90-01 SUP 1 ITEM 1.C TRANSMITTER EXCEPTIONS COMPONENT ID CLASS DESCRIPTION Attachment 1BGFT-11479A ESF CALIBRATION "INTERVAL WITH OIL LOSS. LIFTIME EXCEEDING 32 YEARS.

1BGFT-11479D ESF CAVS FLOW TO RWCU DIFF FLOW ISOL ENHANCED SURVEILLANCE PROGRAM/JUSTIFICATION: SEE 1BBFT-11479A 1SBPT-N052A-C71 RPS HP TURB lST STG STM PRESS ENHANCED SURVEILLANCE PROGRAM: WEEKLY

  • OPERATIONS FUNCTIONAL TEST FOR TURBINE STOP VALVE CLOSURE TO VERIFY*30' POWER BYPASS LOGIC; 18 MONTH CALIBRATION TO ~

CHECK FOR SLUGGISH RESPONSE. ~

  • JUSTIFICATION: THE FUNCTION OF 1SBPT-N052A-C71 THRU N052D-C71 IS TO MEASURE TURBINE FIRST STAGE PRESSURE AND PROVIDE SIGNALS TO AUTOMATICALLY BYPASS THE TURBINE STOP VALVE AND. CONTROL VALVE CLOSURE SCRAM AND EOC-RPT TRIP FUNCTIONS BELOW 30% THERMAL POWER. THIS FUNCTION IS CONTINUOUSLY CHECKED VIA AN.OVERHEAD ANNuNCIATOR THAT ALARMS WHEN ANY ONE OF THE FOUR CHANNELS* IS IN A BYPASS CONDITION; WEEKLY FUNCTIONAL TESTS VERIFY THE INDIVIDUAL STOP VALVE CLOSURE SCRAM FUNCTIONS ARE NOT BYPASSED. LOSS OF TRANSMITTER FILL OIL WOULD RESULT IN LOSS OF RESPONSE TO INCREASING PRESSURE AND SETPOINT DRIFT HIGH; THIS FAILURE MODE WOULD NOT PREVENT RPS OR EOC-RJ>>T TRIP ...

FUNCTIONS; DURING PLANT START-UPS, OPERATIONS.PROCEDURES REQUIRE TESTING TO VERIFY THAT THE TURBINE VALVE SCRAM FUNCTIONS ARE ACTIVATED PRIOR TO EXCEEDING 30% POWER.

1SBPT-N052B-C71 RPS HP TURB lST STG STM PRESS SEE 1SBPT-N052A-C71 1SBPT-N052C-C71 RPS HP TURB lST STG STM PRESS SEE 1SBPT-N052A-C71 1SBPT-N052D-C71 RPS HP TURB lST STG STM PRESS. . SEE 1SBPT-:N052A-C71 Page 3

ATTACHMENT 3 NRC 90-01 SUP 1 ITEM 1.D TRANSMITTERS

  • COMPONENT ID CLASS DESCRIPTION Attachment 1BBLT-3622B PAM REAC LEV~L-POST ACCIDENT MONITOR ENHANCED SURVEILLANCE PROGRAM: 18 MONTH

'CALIBRATION DRIFT TRENDING 1BBLT-3682A PAM REACTOR.LEVEL -*POST ACCIDENT MON ENHANCED SURVEILLANCE PROGRAM: 18 MONTH CALIBRATION DRIFT TRENDING lBBLT-36828 'PAM REACTOR LEVEL - POST ACCIDENT MON ENHANCED SURVEILLANCE PROGRAM: *18 MONTH CALIBRATION DRIFT TRENDING 1BBLT-3683A PAM REACTOR LEVEL - POST ACCIDENT MON .ENHANCED SURVEILLANCE PROGRAM: 18 MONTH CALIBRATION DRIFT TRENDING ...

lBBLT-7854 RSP REACTOR WATER LEVEL-RSP (WIDE RANGE) ENHANCED SURVEILLANCE PROGRAM: 18 MONTH ~

CALIBRATION DRIFT TRENDING lBBLT-7854-1 RSP REACTOR LEVEL SHUTDOWN RANGE ENHANCED SURVEILLANCE PROGRAM: 18 MONTH CALIBRATION DRIFT TRENDING 1BBPT-3684A PAM REACTOR PRESSURE-POST ACCIDENT MON ENHANCED SURVEILLANCE PROGRAM: MONTHLY .

. CHANNEL CHECKS, 18 MONTH CALIBRATION CHECK FOR SLUGGISH RESPONSE; DRIFT TRENDING IS NOT ACCURATE DUE TO RANGE COOE 9.

lBBPT-36848 PAM REACTOR PRESSURE - POST ACCIDENT MON ENHANCED SURVEILLANCE PROGRAM: MONTHLY CHANNEL CHECKS; 18 MONTH CALIBRATION CHECK FOR SLUGGISH RESPONSE; DRIFT TRENDING NOT ACCURATE DUE TO RANGE CODE

9. . .

1BBPT-7853A RSP REAC PRESSURE-RHR INTERLOCK RSP . ENHANCED SURVEILLANCE PROGRAM: 18 MONTH CALIBRATION DRIFT TRENDING 1BBPT-7853D RSP. REAC PRESSURE-RHR *INTE~CK ENHANCED SURVEILLANCE PROGRAM: MONTHLY CHANNEL CHECK; 18 MONTH CALIBRATION CHECK.

FOR SLUGGISH RESPONSE; DRIFT TRENDING NOT ACCURATE DUE TO RANGE CODE 9. . *. *

.Page 1 l_* __._ ____ _

~* :

Public Service Electric and Gas Company Stanley LaBruna public Service Electric and Gas Company P.6. Box 236, Hancocks Bridge, NJ 08038 609-339-1200 Vice President - Nuclear Operations MAR 0 1.1993 NLR-N93028 t,Jnited States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

NRC BULLETIN 88-08 THERMAL STRESSES IN PIPING CONNECTED TO REACTOR COOLANT SY$TEM SALEM GENERATING STATION UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 By let.ter dated January 31, 1992 (Ref: NLR-N91210), Public

.service Electric & Gas Company (PSE&G) provided a response to address the thermal stress concerns of Bulletin 88-08 resulting from valve leakage. PSE&G proposed to e_stablish double isolation valves in the Safety Injection lines, and establish flow in t:pe Auxiliary Pressurizer Spray and* the Alternate Charging lines.

Prior to implementing the proposed changes, PSE&G-committed in this letter to perform an evaluation of the new valve lineups.

PSE&G has completed the evaluations of the new valve lineups.

The proposed change for the Safety Injection lines,: double valve isolation, will alleviate the Bulletin 88-08 concerns. However, implementing this change will isolate a section of piping including the Boron Injection Tank with no overpressurization protection. In order to implement the proposed change, PSE&G will be required to install a thermal relief valve to provide the necessary overpressure protection. PSE&G will also provide additional administrative controls to monitor the isolated section-of Safety Injection piping for under pressure due to thermal contraction~ PSE&G proposes to complete the required modifications during the palem Unit 2 eighth refueling outage, currently. scheduled for the fall of 1994 and during the Salem:

Unit 1 twelfth refueling outage, currently scheduled for the spring of 1995. This schedule will allow sufficient time to obtain the required materials necessary to perform the modifications .

. 9303090277 930301 PDR ADOCK 05000272 0 P-DR

-- MAR 0-11993

-I Document Control Desk* 2 NLR-N93028 The engineering evaluation of the proposed changes to reposition valves to ensure constant flow through the Auxiliary Pressurizer Spray and the Alternate Charging lin_es shows that this change would eliminate-the Bulletin 88-08 concerns.* However, the.

evaluation also concluded that additional concerns such as the potential adverse impact on RCS/CVCS/pressurizer components due to normal operation "in this conf ig~ration supported the need for an alternate solution. Therefore, PSE&G is proposing to perform a detailed thermal fatigue evaluation, including postulated valve leakage transients instead of operating with constant flow through these lines. This fatigue analysis will be based on plant specific conditions to demons~rate a usage factor tha~ will preclude failures. PSE&Gproposes to complete-the required

'analysis by December 31, 1993.

Non-destructive examinations of susceptible welds have been completed during the previous two refueling outages for both Unit l.and Unit 2. No indications of fatigue-related cracks have been found to date. Until the proposed analysis is completed and modifications installed, PSE&G will continue to conduct non-destructive testing (NDE) on the Safety Injection, Auxiliary Pressurizer Spray and Alternate Charging lines during each refueling outage.

I Should there be any questions with regard to this submittal, -I please do not hesitate to contact us~ , I Sincerely,

/J~~

  • .)

MAR 0 1 1993 Document Control Desk 3 NLR-N93028 C Mr. J. c. Stone Licensing Project Manager Mr. T. Johnson Senior Resident Inspector Mr. T. Martin, Administrator Region I Mr. Kent Tosch, Chief New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nucle.ar Engineering CN 415

  • Trenton, NJ 08625

Public Service Electric and Gas Company Steven*E. Miltenberger Public Service Electric and Gas Company P.O. Box 23.6, Hancocks Bridge, NJ 08038 609-339-4199 Vice President and Chief Nuclear O.llicer OCT28 1992 NLR-N92144 U. s. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

.Gentlemen:

COMPLETION OF REQUIRED ACTIONS UNDER IE BULLETIN 88-10 MOLDED CASE CIRCUIT BREAKERS SALEM AND HOPE CREEK GENERATING STATIONS.

DOCKET NOS~ 50-272, 50-311, AND 50-354 On November 1; 1989, Public Service Electric and Gas Company (PSE&G) forwarded its response (NLR-N89225) to IE Bulletin 88-10, Supplement 1.

  • Tpat response provided a commitment to~ l}

- - --- establish_ trac_eabil_i1:y _for molded case circuit breakers (MCCB) purchased between August- 1; -f983 and -.Augtist-1-,-

  • I98S- a-nd- instal-led- - - - --- - - I in safety-related applications, and 2) replace MCCB's identified under Item 1 which were determined to be non-traceable. PSE&G committed to.complete review/replacement of non-traceable MCCB's.

prior to restart.from the tenth, sixth and fourth refueling outages for Salem Units 1 and 2, and Hope Creek, respectively.

The status of these activities is summarized in the following paragraphs.

All committed activities relating to. IE Bulletin 88-iO for Salem.*

Unit 1 were accomplished in accordance with the committed schedule. *completion of Unit 2 activities was delayed somewhat due to availability of replacement breakers. This delay was discussed with the NRC LiGensing Project Manager for Salem, Mr. J. Stone, and determined to be acceptable. All committed activities relating to IE Bulletin 88-10 for Salem Unit 2 are complete at this time.

PSE&G had committed to complete all review/replacement activities for Hope Creek prior to restart from the fourth refueling outage which is presently underway. The traceability review of MCCB's purchased during the identified period was successful in all cases and therefore no replacements were required at Hope Creek.

As such, all committed activity relating-to IE Bulletin 88-10 is

. complete for Hope Cr.eek also.

9211040183 921028 PDR ADOC~ 05000272 P PDR

. *-- __.........--~*- .

'j Document Control Desk .2 OCT2 8 1992 NLR-N92144 Completion of these activities fulfills the requirements of IE Bulletin*88-10 and its supplement for Salem.and Hope Creek Generating Stations. . .

If there are any questions regarding this information, please feel free to contact us.

Sincerely, c Mr. T. T. Martin, Administrator - Region I

u. s. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. J. c. Stone, Licensing Project Manager U~ S~ Nuclear Regulatory Commission
  • -one- White Flint*North. -- - -- ----- -- -

11555 Rockville Pike Rockville, MD 20852 Ms. A. Keller U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. T. P. Johnson (S09)

USNRC Senior Resident Inspector Mr. K. Tosch, Chief NJ Department of Environmental Protection Division of Environmental Quality Bureau of-Nuclear*Engineering CN 415 Trenton~ NJ 08625

\

August 10, 1992 Docket Nos. 50-272, 50-311, and 50-354 Mr. Steven E. Miltenberger Vice President and Chief Nuclear Officer Public Service Electric and Gas Company Post Office Box 236 Hancocks Bridge, New Jersey 08038

Dear Mr. Miltenberger:

SUBJECT:

RESPONSE TO NRC BULLETIN 92-01, "FAILURE OF THERMO-LAG 330 FIRE BARRIER SYSTEM", SALEM NUCLEAR GENERATING STATION, UNITS 1 AND 2 AND HOPE CREEK GENERATING STATION (TAC NOS. M83925, M83926 AND M83884)

Your letter dated July 22, 1992, provided a response to NRC Bulletin 92-01 for Salem Nuclear Generating Station, Units 1 and 2, and Hope Creek Generating Station. Your response stated that Salem and Hope Creek do not have Thermo-Lag 330 installed as a fire barrier for small diameter conduit or wide trays which provide safe shutdown capability. Your confirmation provides an adequate basis to consider NRC's review of your response complete. Further NRC review, if any, will be performed by inspection or audit.

Sincerely,

/S/

James C. Stone, Senior Project Manager Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation cc: See next page DISTRIBUTION:

Docket File CMi 11 er ACRS (10)

NRC & Local PDRs MO'Brien(3) EWenzinger, RGN-1 PDI-2 Reading JStone JWhite, RGN-1 SVarga AKell er PMadden, 80-1 JCalvo OGC AMasciantonio, 13D-18 PDl-2/PE PDl-2/PM PDl-2/D

~I OFFICE I

NAME CMILLEt; DATE I D

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 August 10, 1992 Docket Nos. 50-272, 50-311, and 50-354 Mr. Steven E. Miltenberger Vice President and Chief Nuclear Officer Public Service Electric and Gas Company*

Post Office Box 236 Hancocks Bridge, New Jersey 080~8

Dear Mr. Miltenberger:

SUBJECT:

RESPONSE TO NRC BULLETIN 92-01, "FAILURE OF THERMO-LAG 330 FIRE BARRIER SYSTEM", SALEM NUCLEAR GENERATING STATION, UNITS 1 AND 2 AND HOPE CREEK GENERATING STATION (TAC NOS. M83925, M83926 AND M83884)

Your letter dated July 22, 1992, provided a response to NRC Bulletin 92-01 for Salem Nuclear Generating Station, Units 1 and 2, and Hope Creek Generating Station. Your response stated that Salem and Hope Creek do not have Thermo-Lag 330 installed as a fire barrier for small diameter conduit or wide trays which provide safe shutdown capability. Your confirmation provides an adequate basis to consider NRC's review of your response complete. Further NRC review, if any, will be performed by inspection or audit.

Sincerely,

~cb James C. Stone, Senior Project Manager Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation cc: See next page

Mr. Steven E. Miltenberger Salem Nuclear Generating Station, Public Service Electric & Gas Units 1 and 2, and Company Hope Creek Generating Station cc:

Mark J. Wetterhahn, Esquire Richard Hartung Winston & Strawn Electric Service Evaluation 1400 L Street NW Board of Regulatory Commissioners Washington, DC 20005-3502 2 Gateway Center, Tenth Floor Newark, NJ 07102 Richard Fryling, Jr., Esquire Regional Administrator, Region I Law Department - Tower 5E U. S. Nuclear Regulatory Commission 80 Park Place 475 Allendale Road Newark, NJ 07101 King of Prussia, PA 19406 Mr. Calvin A. Vondra Lower Alloways Creek Township General Manager - Salem Operations c/o Mary 0. Henderson, Clerk Salem Generating Station Municipal Building, P.O. Box 157 P.O. Box 236 Hancocks Bridge, NJ 08038 Hancocks Bridge, NJ 08038 Mr. Frank X. Thomson, Jr., Manager Mr. S. LaBruna Licensing and Regulation Vice President - Nuclear Operations Nuclear Department Nuclear Department P.O. Box 236 P.O. Box 236 Hancocks Bridge, NJ 08038 Hancocks Bridge, New Jersey 08038 Mr. David Wersan Mr. Thomas P. Johnson, Senior Resident Assistant Consumer Advocate Inspector Office of Consumer Advocate Salem Generating Station 1425 Strawberry Square U.S. Nuclear Regulatory Commission Harrisburg, PA 17120 Drawer I Hancocks Bridge, NJ 08038 Mr. J. A. Isabella MGR. - Generation Department Dr. Jill Lipoti, Asst. Director Atlantic Electric Company Radiation Protection Programs P.O. Box 1500 NJ Department of Environmental 1199 Black Horse Pike Protection Pleasantville, NJ 08232 CN 415 Trenton, NJ 08625-0415 Carl D. Schaefer External Operations - Nuclear Maryland People's Counsel Delmarva Power & Light Company American Building, 9th Floor P.O. Box 231 231 East Baltimore Street Wilmington, DE 19899 Baltimore, Maryland 21202 Public Service Commission of Maryland Mr. J. T. Robb, Director Engineering Division Joint Owners Affairs ATTN: Chief Engineer Philadelphia Electric Company 231 E. Baltimore Street 955 Chesterbrook Blvd., 51A-13 Baltimore, MD 21202-3486 Wayne, PA 19087

_J

r-----

Mr. Steven E. Miltenberger Salem Nuclear Generating Station, Public Service Electric & Gas Unit 1 and 2, and Company Hope Creek Generating Station cc:

Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 241 Hancocks Bridge, New Jersey 08038 Mr. J. J. Hagan General Manager - Hope Creek Operations Hope Creek Generating Station P.O. Box 236 Hancocks Bridge, New Jersey 08038

_J

Retrieved from "https://kanterella.com/w/index.php?title=ML18096B336&oldid=2505658"