NRC-93-0061, Application for Amend to License NPF-43,revising TS to Extend Instrument Calibr Intervals to 36 Months for Selected Instrumentation,Per BWROG Licensing Topical Rept NEDC-32160P,Dec 1992.GE Proprietary Rept Encl.Rept Withheld

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Application for Amend to License NPF-43,revising TS to Extend Instrument Calibr Intervals to 36 Months for Selected Instrumentation,Per BWROG Licensing Topical Rept NEDC-32160P,Dec 1992.GE Proprietary Rept Encl.Rept Withheld
ML20046B260
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 07/29/1993
From: Gipson D
DETROIT EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML19310D552 List:
References
CON-NRC-93-0061, CON-NRC-93-61 NUDOCS 9308030421
Download: ML20046B260 (14)
v • d • e


Text

"

Y Douglas R Gapson T.r ..s r i <a<s+4

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Detroit -

. m ,_

EC ISOn v July 29, 1993 NRC-93 -0061 U. S. Nucleac Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555

References:

1) Fermi 2 NRC Docket No. 50-341 NRC License No. NPF-43
2. ) "EWh Owners ' Group Licensing Topical Report -

Calibra tion Interval Extension," NEDC-32160P, December 1992

3) Detroit Edison letter to NRC, "D e t roit Edison Response to NRC Bulletin 90-01, Supplement 1,"

NRC-93 -0 03 7, datcd March 5, 1993

Subject:

Proposed Technical Specification Change (Licence Amendment) - Calibration Interval Extension Pursuant to ICCFR50.90 Detroit Edison Company hereby proposes to amend Operating License NPF-43 for the Fermi 2 plant by incorporating the enclosed changes into the Plant Technical Specifications. The proposed change extends instrument calibration intervals for celected instrumentation to 36 months.

The proposed Technical Specification changes are supported by an analysis performed by the EWR Csmers' Group (Reference 2), which demonstrates that other periodic tests required by Technical Specifications, such as channel checks, channel functional tests, logic system functional tests, are adequate to assure performance within acceptance limits. The applicability of the reference analysis techniques to Fermi 2 has been verified. In addition, General Electric has per formed an analysis of other instruments used at Fermi 2 using the Reference 2 techniques.

Detroit Edison's evaluation of the proposed change as well as the accompanying signifiermt hazards consideration analysis is provided as Enclosure 1. The General Electric plant-specific report is provided as Enclosure 2. The proposed Technical Specification page changes are provided as Enclosure 3.

This proposal will reduce equipment wear f rom unnecessary t est cycles, reduce out-of-service time due to calibration and reduce Engineered fp 030007 p g i ')

9aOeOaO m 920 m PDR ADDCK 05000241 n Mq P ppR , f

i USNRC July 29, 1993 NRC-93-0061  ;

Page 2  !

J Safety Feature actuations. In addition, the change involves a ,

significant cost savings ~ by eliminating a significant amount of instrument calibration work from each refueling outage scope. This elimination will save at least 2.2 million dollars - (in current '

dollars) over the remainder of the current operating license. ~

I' Detroit Edison has evaluated the proposed Technical Specifications against the criteria of 10CFR50.92 and determined that no significant j hazards consideration is involved. ' The Fenmi 2 Onsite Review .

Organization has approved and the Nuclear Safety Review Group has reviewed the proposed Technical Specifications and concurs with the t enclosed determinations. In accordance with 10CFRSO.91, Detroit ,

Edison has provided a copy of this letter to the State of Michigan.- ,

The information in Enclosure 2 to this letter has been identified by General Electric (GE) as proprietary information. Included in Enclosure 2 is GE's affidavit to that effect. Therefore,' in accordance with 10CFR2.790, it is requested that Enclosure 2 be .I withheld from public disclosure.  !

t If you have any questions, please contact Mr. Glen D. Ohlemacher at j (313) 586-4275.

Sincerely, f t

Enclosure [

cc: T. G. Colburn  !

W. J. Kropp  !

J . B. Ma rtin i M. P. Phillips f Supe rvis or, Electric Operators, Michigan Public Service Commission - J. R. Padgett h

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G r

USNRC 4

July ~29, 1993 NRC-93-0061 Page 3 i

l I, DOUGLAS R. GIPSON, do hereby af firm that the foregoing statements are based on f acts and circumstances which are true and accurate to ,

the best of my_ knowledge and belief.

y + Y DOUGLAS R. GIPSON Senior Vice President On this day of __ t /hdr . 1993, before me .

hon, personally appeared that he executed the Douglas foregoingR.asj Gip /his free act and deed.peir g first duly sworn and say i

h 14Lw 4/ W C' Notary Public NOTARYMONROE PUBUCSTm OF MODCm UyJNry i 1

N NWalON EXP. NOV. M1095 h l

1 4

-- d, Enclosure 1 t,o NRC-93-0061 Page 1 i

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ENCLOSURE 1 EVALUATION OF PROPOSED CHANGE AND NO SIGNIFICANT HAZARDS EVALUATION 1

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Enclosure 1 to NRC-93-0061 Page 2 INTRODUCTION This proposed change is to extend instrument calibration intervals to 36 months for selected instrumentation. Industry experience has demonstrated that other periodic tests required by Technical Specifications, such as channel checks, channel functional tests, and logic system functional tests provide adequate assurance that instrument performance is within acceptance limits.

EVALUATION An analysis technique has been developed by General Electric for the BWR Owners' Group which provides the basis for justifying instrument drift allowances based on as-found, as-left data (Reference 2). The analysis was performed for representative BWR instrumentation, and the results are applicable to Fermi 2. In addition, General Electric has performed a plant specific evaluation to extend the Reference 2 evaluation to additional instrumentation (Enclosure 2). The Enclosure 2 evaluation is intended to be used in conjunction with the Reference 2 report.

Plant operating experiences were reviewed to identify instrument failures and how they were detected. The failures were identified or would have been identified by other testing requirements contained in Technical Specifications (channel check, channel functional test, and logic system functional test) and by operators. The exception to this statement is the Rosemount pressure transmitter slow loss of fill-oil phenomenon discussed below.

These other tests are normally sufficient to identify failure modes or degradations in instrument performance and assure operation of the analyzed instrument loops within acceptance limits.

The evaluations of Reference 2 and Enclosure 2 demonstrate that the calibration interval can be extended to 36 months for the instrumentation listed in Table 1.

In each case, the functional unit involved is monitored by regular channel checks required by the Technical Specifications. Also, the instrumentation involved has either been evaluated in Reference 2 or the Enclosure 2 extension of Reference 2. The appropriate document is

, indicated in Table 1.

For this instrumentation, the instrument drift determined in Reference 2 or Enclosure 2 was used in conjunction with the NRC approved General Electric Instrument Setpoint Methodology (NEDC-31336). These

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NRC-93-0061  :

Page 3 i

i evaluations were performed using a calibration frequency of 45 months, corresponding to the proposed 36 month frequency plus the 25% overrun '

allowed by Specification 4.0.2. The evaluations determined that no change to the Trip Setpoints or Allowable Values specified in the Technical Specifications is needed to accommodate the extended l calibration frequency. l A concern related to calibration extension is the phenomenon of slow loss of fill-oil in Rosemount pressure transmitters. Detroit Edison  ;

has committed to remove all remaining Rosemount pressure transmitters j of concern by the completion of Fermi 2's fourth refueling in the l spring of 1994 (Reference 3). Thus, the slow fill-oil loss concern j

does not impact the proposed change since the earliest implementation  ;

for this change is also the fourth refueling. l l

The calibration extension is proposed to be implemented in a staggered fashion. Each functional unit proposed for extension consists of at least two channels. The proposed TS will require at least one-half of the channels for each functional unit to be tested at least every 18 months. This requirement is applied by a ** footnote to Technical

]

Specification Table 1.1 where appropriate, or by wording in the l Surveillance Requirement itself. I This staggering will assure that at least one channel for each functional unit is calibrated at least once every 18 months. This will provide a means to detect generic problems within a functional  ;

unit without waiting a possible 36 months or more between  ;

calibrations. '

The TS included in the Reference 2 Topical Report includes a change to the Specification 1.19 definition of Logic System Functional Test j (LSFT). The change allows the sensor to be excluded from the LSFT.

1 The sensor functionality is tested during the channel calibration. ,

LSFT's are performed typically at an 18-month interval. In order to i obtain the benefits of the calibration interval extension the sensor j must be excluded from the LSFT definition. This is acceptable since l the reliability of sensor performance is monitored by periodic channel check surveillances.

SIGNIFICANT I!AZARDS CONSIDERATION In accordance with 10CFR50.92, Detroit Edison has made a determination that the proposed amendment involves no significant hazards considerations. To make this determination, Detroit Edison must establish that operation in accordance with the proposed amendment i

. to NRC-93-co61 Page 4 would not: 1) involve a significant increase in the probability or consequences of an accident previously evaluated, or 2) create the possibility of a new or different kind of accident from any accident previously evaluated, or 3) involve a significant reduction in a margin of safety.

The proposed change to extend to 36 months the calibration interval of selected instrumentation does not:

1) Involve a significant increase in the probability or consequences of an accident previously evaluated. The purpose of the proposed Technical Specification change is to extend calibration interval testing requirements for selected instrumentation. Ilowever, s because of the continued application of redundant Technical Specification requirements such as channel checks, channel l functional tests, and logic system functional tests, the '

performance of these instruments will be maintained within the l

acceptance limits assumed in plant safety analyses and required for successful mitigation of an initiating event. The proposed Technical Specification changes do not affect the capability of the associated systems to perform their intended function within their instrument settings.

These other tests are sufficient to identify failure modes or degradations in instrument performance and ensure operation of the associated systems within acceptance limits. There are no credible failure modes that can be detected by instrument calibration that cannot also be detected by other Technical Specification tests.

2) Create the possibility of a new or different kind of accident from any accident previously evaluated. As discussed above, the '

proposed Technical Specification changes do not affect the  ;

capability of the associated systems to perform their intended l function within the acceptance limits assumed in plant safety analyses and required for successful mitigation of an initiating event. All plant systems continue to operate in an identical  !

manner. No new accident modes are created.

3) Involve a significant reduction in a margin of safety. The current Technical Specification allowable values are based on the maximum analytical limits assumed in the plant safety analyses.

These analyses conservatively establish the margin of safety.

The proposed Technical Specification changes do not affect the capability of the associated systems to perform their intended function within the instrument settings used as the basis for the plant safety analyses. Plant and system settings to an

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Page 5 initiating events will remain in compliance within the assumptions of the safety analyses, and therefore the margin of safety is not affected.

Although not explicitly evaluated, the proposed Technical Specification changes may increase the margin of safety by:

o Heducing the amount of time that systems are out-of-service for the performance of instrument calibration.

o Reducing actuations of Engineered Safety Features, o Reducing wear-and-tear on equipment resulting from unnecessary test cycles.

Based on the above, Detroit Edison has determined that the proposed amendment does not involve a significant hazards consideration.

ENVIRONMENTAL IMPACT Detroit Edison has reviewed the proposed Technical Specification changes against the criteria of 10CFR51.22 for environmental considerations. The proposed change does not involve a significant hazards consideration, nor significantly change the types or significantly increase the amounts of effluents that may be released '

offsite, nor significantly increase individual or cumulative occupational radiation exposures. Based on the foregoing, Detroit Edison concludes that the proposed Technical Specifications do meet the criteria given in 10CFR51.22(c)(9) for a categorical exclusion from the requirements for an Environmental Impact Statement.

CONCLUSION Based on the evaluation above: 1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and 2) such activities will be conducted in compliance with the Commission's regulations and proposed amendments will not be inimical to the common defense and security or to the health and safety of the public.

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Enclosure 1 to Table 1 NRC - 93 0061 Instrumeriiation For Extension of Calibration interval to 36 Months Pace 6 - 11 Signal Indicator /

Conditioner: Recorder:  !

Sensor Sensor Trip Unit Trip Unit (Manufacturer / (Manufacturer / Analysis Tech Spec Description Manufacturer Model No Manufacturer Model No Model No) Modei No) ' Report 4.3.1.1-1 Reactor Protection System Instrumentation ,

BWROG Reactor Vessel Steam Dome Pressure-High 510/71000 NA NA **

4.3.1.1 -1.3 Rosemount 1153 Rosemount j 4.3.1.1-1.4 Reactor Vessel Low Water Level-Level 3 Rosemount 1153 Rosemount 510DU NA NA BWROG 4.3.1.1-1.7 Drywell Pressure-High Rosemount 1153 Rosemount 5100U NA NA BWROG 4.3.2.1-1 Isolation Actuation instrumentation 4.3.2.1 1.1 Primary Containment isolation l t

4.3.2.1-1.1.a.1 Reactor Vessel Low Water Level-Level 3 Rosemount 1153 Rosemount 510DU NA NA BWROG  !

4.3.2.1-1.1.a.2 Reactor Vessel Low Water Level-Level 2 Rosemount 1153 Rosemount 510DU NA NA BWROG  ;

4.3.2.1 -1,1.a.3 Reactor Vessel low Water Level. Level 1 Rosemount 1153 Rosemount 510/710DU NA NA BWROG 4.3.2.1-1.1.b Drywell Pressure-High Rosemount 1153 Rosemount 510DU NA NA BWROG ,

5 4. m ' l 1.c.2 Main Steam Line Pressure-Low Rosemount 1151 Rosemount 510/710DU NA NA BWROG 510/

4.3. 2.1 - 1.1.c. 3 Main Steam Line Flow-High Rosemount 1151 Rosemount 710DU NA NA BWROG 122-4.3.2.1-1.1.d Main Steam Line Tunnel Temperature- High PYCO '

1021-04 Rosemount 510DU NA NA BWROG .!

4.3.2.1-1.1.e Condenser Pressure - High Rosemount 1151 Rosemount 510DU NA NA BWROG 122-

+

4.3.2.1 - 1.1. f : Turbine Bldg Area Tempera +ure- High PYCO 1021 44 Rosemount 510DU NA NA BWROG 4.3.2.1-1.2 Reactor Water Cleanup System isolation .

Heat Exchanger / Pump / High Energy Piping Area 4.3.2.1-1.2.b Temperature-High PYCO

  • 102-9093 Riley 86A NA NA BWROG Heat Exchanger / Pump / Phase Separator Area l 4.3 2.1 -1.2.c Ventilation Dif ferential Temperature -High PYCO
  • 102-9093 Riley 86A NA NA BWROG 1 l 4.3.2.1-1.2.e Reactor Vessel low Water Level-Level 2 Rosemount 1153 Rosemount 510Dt) NA NA BWROG' i '

i ' Operability verification is performed as per Channel Calibration definition (1.4) of Fermi 2 Tech Spec.

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,_- . . _ _ . _ _ . . . _ _ . . . _ . ____.._._,_.__..m.m_.___. _ _.... _ __ _.-

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Enclosure 1 to Table 1 NRC 0061 instrumentation For Extension of Calibration interval to 36 Months Page 7 - 11 Signal Indicator /

Conditioner: Recorder:

Sensor Sensor Trip Unit Trip Unit (Manufacturer / (Manufacturer / Analysis Tech Spec Description Manufacturer Model No Manufacturer Model No Model No) Model Nc) Report 4.3.2.1-1.3 Reactor Core Isolation Cooling System isolation l

4.3.2.1-1.3.a.1 RCIC Steam Line Flow riigh, Differential Pressure Rosemount 1151 Rosemount 510DU NA NA B'NROG 4.3.2.1-1.3.b RCIC Steam Supply Pressure-Low Rosemount 1151 Rosemount 510DU NA NA BWROG 4.3.2.1-1.3.c RCIC Turbine Exharst Diaphragm Pressure-High Rosemount . 1151 Rosemount 510/7100U NA NA BWROG N145C 4.3.2.1 1.3.d RCIC Equipment Room Temperature-High GE

  • 3224P1 Riley 86A NA NA BWROG

- 4.3.2.1-1.4 High Pressure Coolant injection System isolation 4.3.2.1-1.4.a.1 HPCI Steam Line Flow-High, Differentiat Pressure Rosemount 1153 Rosemount 710DU NA NA BWROG 4.3.2.1-1.4.b HPCl Steam Supply Pressure-Low Rosemount 1153 Rosemount 510/710DU NA fsA BWROG 4.3.2.1-1.4.c HPCI Turbine Exhaust Diaphragm Pressure-High Rosemount 1153 Rosemount 510/710DU NA NA BWROG N145C 4.3.2.1-1.4.d HPCI Equipment Room Temt pture-High GE 3224P1 Riley 86A NA lNA BWROG

.3.2. 1 -1.5 RHR System Shutdown Cooling Mode Isolation 4.3.2.1 -1. 5.a Reactor Vessel Low Water level-Level 3 Rosemount 1153 Rosemount 510DU NA NA BWROG Reactor Vessel (Shutdown Cooling Cut-in Permissive 4.3.2.1-1.5.b Interlock) Pressure-High Rosemount 1153 Rosemount 510/710DU NA NA BWROG 4.3.2.1-1.6 Secondary Containment Isolation 4.3. 2.1 -1. 6.a Reactor Vessel low Water level-level 2 Rosemount 1153 Rosemount 5100U NA NA BWROG 4.3.2.1 -1.6.b Drywell Pressure-High Rosemount 1153 Rosemount 510DU NA NA BWROG

  • Operability verification is performed as per Channel Calibration definition (1.4) of Fermi 2 Tech Spec.

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-.- _.  :--.4. - - . - . = - - - . .e--...- -- - - - - -,--- . - - - - . ., ,,. .m ..-,-2 r - .--.,,.--.,-..-m ,--.,,..r.,.--..e.-- -_ e-+-..-..v-+.--rw--,--.-r-- . . ~ , - . - . ..-...-w. ---.,--o.m--'

Enclosure 1 to Table 1 NRC 0061 Instrumentation For Extension of Calibration Interval to 36 Months Page 8 - 11 Signal indicator /

Conditioner: Recorder:

Sensor Sensor Trip Unit Trip Unit (Manufacturer / (Manufacturer / Analysis Tech Spec Description Manufacturer Model No Manufacturer Model No Model No) Model No) Report Emergency Core Cooling System Actuation instrumentation '

4.3.3.1-1 4.3.3.1 -1.1 Core Spray System 4.3.3.1-1,1.a Reactor Vessel low Water Level-level 1 Rosemount 1153 GE 184C5988 NA NA BWROG 4.3.3.1-1.1.b Drywell Pressure-High Rosemount 1153 Rosemount 510DU NA NA BWROG 4.3.3.1-1.1.c Reactor Steam Dome Pressure-Low Rosemount 1153 Rosemount 510/710DU NA NA RWhOd 4.3.3.1-1.2 Low Pressure Coolant injection Mode of the RHR System 4.3.3.1-1.2.a Reactor Vessel Low Water Level-Level 1 Rosemount 1153 GE 184C5988 NA NA BWROG 4.3.3.1-1.2.b Drywell Pressure-High Rosemount 1153 Rosemount 510DU NA NA BWROG 4.3.3.1-1.2.c Reactor Steam Dome Pressure-Low Rosemount 1153 Rosemount 510/710DU NA NA BWROG 4.3.3.1-1.2.d Reactor Vessel Low Water Level-level 2 Rosemount 1153 GE 184C5988 NA NA BWROG 4.3.3.1 -1.2.e Reactor Steam Dome Pressure-Low Rosemount 1153 Rosemount 510/710DU NA NA BWROG 4.3.3.1-1.2.f Riser Differential Pressure-High Rosemount 1153 Rosemount 510/710DU NA NA BWROG 4.3.3.1-1.2.g Recirculation Pump Differential Pressure-High Rosemount 1153 Rosemount 510/710DU NA NA BWROG 4.3.3.1 -1.3 High Pressure Coolant injection System 4.3.3.1 -1.3.a Reactor Vessel Low Water Level-Level 2 Rosemount 1153 GE 184C5988 NA NA BWROG 4.3.3.1-1.3.b Drywell Pressure-High Rosemount 1153 Rosemount 510DU NA NA BWROG 1151/

4.3.3.1-1.3.c Condensate Storage Tank Level-Low Rosemount 1152 Rosemount 5100U NA NA BWROG 4

4.3.3.1-1.3,e Reactor Vessel High Water Level-level 8 Rosemount 1153 GE 184C5988 NA NA BWROG e

r*~ase- w e5 - =----w m e we- o-+m--m-v r ere-.-m+- e,we--- +>-wwee we- m %-e-- s e-eme- ew .ct rww --3ei r- -+-- e e m an- * + we e v e e .w rwe-e - -

  • w w er --e -s *=,c . ,,. .rw,. ,-.4 ...cw.n ~-,.w,c.,a ,,...-,-..,..w. r-,,qw-=.,,,,. ..m.w.,em'

Enclosure 1 to Table 1 NRC 0061 instrumentation For Extension of Calibration Interval to 36 Months Page 9 - 11 Signal Indicator /

Conditioner: Recorder:

Sensor Sensor Trip Unit Trip Unit (Manufacturer / (Manufacturer / Analysis Tech Spac Description Manufacturer Model No Manufacturer Model No Model No) Model No) Report 4.3.3.1 1.4 Automatic Depressurization System l

4.3.3.1-1.4.a Reactor Vessel Low Water Level-Level 1 Nsemount 1153 GE 184C5988 NA NA BWROG 4.3.3.1-1.4.b Dryweil Pressure-High Rosemount 1153 Rosemount 510/710DU NA NA BWROG l 4.3.3.1-1.4.d Core Spray Pump Discharge Pressure-High Rosemount 1153 Rosemount 510/710DU NA NA BWROG 4.3.3.1-1.4.e RHR LPCI Mode Pump Discharge Pressure-High Rosemount 1153 Rosemount 510/710D0 NA NA BWROG 4.3.3.1 - 1.4.f Reactor Vessel Low Water level-level 3 Rosemount 1153 Rosemount 510/710DU NA NA BWBOG 4.3.4-1 ATWS Recirculation Pump Trip Actuation Instrumentation 4.3.4 1.1 Reactor Vessel Low Water level-Level 2 Rosemount 1153 GE 184C5988 NA NA BWROG 4.3.4-1.2 Reactor Vessel Pressure-High Rosemount 1153 GE 184C5988 NA NA BWROG 4.3. 5.1 -1 Reactor Core Isolation Cooling System Actuation Instrumentation 4.3.5.1 1.a Reactor Vessel Low Water Level-level 2 Rosemount 1153 GE 184C5988 NA NA BWROG 4.3.5.1-1.b Reactor Vessel High Water Level-Level 8 Rosemount 1153 GE 184C5988 NA NA BWROG 1151/

, 4.3.5.1-1.c Condensate Storage Tank Level-Low Rosemount 1152 Rosemount 510DU NA NA BWROG 4.3.7.4-1 Remote Shutdown Monitoring Instrumentation Analogic / Pl j 4.3. 7.4 - 1.1 Reactor Vessel Pressure Rosemount 1152 NA NA NA 2455 BWROG 4.3.7.4-1.2 Reactor Vessel Water Level Rosemount 1153 GE 184C5988 TEC/156M Weston/1316 BWROG Transmation/

! 4.3.7.4-1.3 Suppression Chamber Water Temperature Conax

  • 7N62 NA NA 610T Weston/1316 BWROG Analogic / Pi .

4.3.7.4-1.4 Drywell Pressure Rosemount 1153 NA NA NA 2455 BWROG I Hays Republic /

4.3.7.4-1.5 RHR Division i Hx Discharge Flow Rosemount 1153 NA NA GEMAC/ 565 3600 BWROG

  • Operability verification is performed as per Channel Calibration definition (1.4) of Fermi 2 Tech Spec.

Enclosure 1 to Table 1 NRC - 93 0061 Instrumentation For Extension of Calibration Interval to 36 Months Page 10 - 11 Signal Indicator / -

I Conditioner: Recorder:

Sensor Sensor Trip Unit Trip Unit (Manufacturer / (Manufacturer / Analysis Tech Spec Description Manufacturer Model No Manufacturer Model No Model No) Model No) Report .

4.3.7.5-1 Accident Monitoring Instrumentation L&N/Speedo 4.3.7.5-1.1 Reactor Vessel Pressure Rosemount 1152 NA NA NA Max M BWROG Weston/1316 &

L&N/

4.3.7.5-1.2.a Reactor Vessel Water Level-Fuel Zone Rosemount 1153 Rosemount 510DU NA SpeedoMax M BWROG L&N/ Speedo 4.3.7.5-1.2.b Reactor Vessel Water Level Wide Range Rosemount 1153 GE 184C5988 NA Max M BWROG L&N/ Speedo ,

4.3.7.5-1.3 Suppression Chamber Water Level Rosemount 1153 NA NA NA Max M BWROG Westronics/

4.3.7.5-1.4 Suppression Chamber Water Temperature Conax

  • 7080 NA NA NA 3000C BWROG Westronics/  !

4.3.7.5-1.5 Suppression Chamber Air Temperature Conax '

7880 NA NA NA 3000C BWROG Westronics/

4.3.7.5-1.6 Suppression Chamber Pressure Rosemount 1153 NA NA NA 2100C BWHOG Westronics/

4.3.7.5-1.7 Drywell Pressure, Wide Range Rosemount 1153 NA NA NA 2100C BWROG Westronics/

4.3.7.5-1,8 Drywell Air Temperature Conax

  • 7B80 NA NA NA 3000C BWROG 4.3.9.1-1 Feedwater/ Main Turbine Trip Actuation Instrumentation 4.3.9.1-1.3 Reactor Vessel High Water Level-Level 3 Rosemour.t 1153 Rosemount 510/710DU NA NA BWROG 4.3.11.1-1 Appendix R Alternative Shutdown Instrumentation 4.3.11.1-1.5 Condensate Storage Tank Level Rosemount 1151 NA NA NA Chessell/ 700 BWROG 4.3.11.1-1.7 Reactor Water Level Rosemount 1153 NA NA NA Chessell/ 700 BWROG Transmation/ Foxboro/

, 4.3.11.1-1.8 Reactor Pressure Rosemount 1153 NA NA 230T 6402HC BWROG Thermoelectric Transmation/

4.3.11.1-1.9 Torus Water Temperature

  • 1T3210A NA NA 610T Chessell/ 700 BWROG 4.3.11.1-1.10 Torus Water Level Rosemount 1151 NA NA NA Chessell/ 700 BWROG Thermoelectric Transmation/

4.3.11.1-1.11 Primary Containment Temperature

  • AD14TUR NA NA G10T Chessell/ 700 BWROG
  • Operability verification is performed as per Channel Calibration definition (1.4) of Fermi 2 Tech Spec.

4

, _y,~_-,-, ,#.--.,  %-g,-.n._,,- ,,..,-,2 e m r e- mw~ -~

m-- = = w---- .- w-.-- ww w~ w --*wwwe--v---. +r---==---e- =v--wmv-ne-e'v--~*-ewe--- s ---e.w=m *v- 1 +-m=h--%-- - - - - - -* - * -e--wi -ew& -wwau ce - w w nT

Enclosure 1 to Table 1 - '

NRC - 934061 Instrumentation For Extension of Calibration Interval to 36 Months Page 11 - 11 Signal Indicator /

Conditioner: Recorder:

Sensor Sensor Trip Unit Trip Unit (Manufacturer / (Manufacturer / Analysis ,

Tech Spec Description Manufacturer Model No Manufacturer Model No Model No) Model No) Report '

4.4.2.2 Safety / Relief Valves Low-Low Set Function 4.4.2.2.b CHANNEL CAllBRATION at least once per 36 months Rosemount 1153 GE 184C5988 NA NA BWROG 4.6.1.4 Primary Containment / MSIV Leakage Control System Foxboro/ 6402

!- N2AO-L2C- Foxboro/ N2Al- & Hays Republic / BWROG/

4.6.1.4.d.3 CHANNEL CAllBR ATION at least once per 36 months Rosemount 1153 Foxboro R 13V 3600 GE 4.6.2 Depressurization Systems / Suppression Chamber Verify eight suppression pool water temperature instrumentation channels OPERABLE by performance of a CHANNEL CAllBRATION at least once per 36 Westronics/ j 4.6.2.1.f.3 months,. Conax

  • 7B80 NA NA NA 2400 BWROG Verify both narrow range suppression chamber water levelinstrumentation channels OPERABLE by performance of a CHANNEL CALIBRATION at least N2AP+ Foxboro/ N2Al- BWROG /

4.6.2.1.g.3 once per 36 months. Rosemount 1153 Foxboro ALM-AR 13V Weston/1316 GE

  • Operability verification is performed as per Channel Calibration definition (1.4) of Fermi 2 Tech Spec.
  • GE - General Electric Plant Specific Report, Enclosure 2.

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