Text

Forwards Rev 9 to Fermi 2 Ufsar,Per 10CFR50.71(e) & 10CFR50.4(b)(6).Summary of Changes to QA Program & Vol 1 of Technical Requirements Manual,Encl
	ML20206C245
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Site:	Fermi
Issue date:	04/26/1999
From:	Gipson D; DETROIT EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
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ML20206C251	List: NRC-99-0037, Forwards Rev 9 to Fermi 2 Ufsar,Per 10CFR50.71(e) & 10CFR50.4(b)(6).Summary of Changes to QA Program & Vol 1 of Technical Requirements Manual,Encl;
References
	CON-NRC-99-0037, CON-NRC-99-37 NUDOCS 9904300206
	Download: ML20206C245 (47)
	v • d • e

Doudas R. Gipson

, Senior Vice lYesident, Nuclear Generation Fermi 2 6400 North Dixie lluy, Newport, Michigan 48166 Tel: 734.586.5201 Fat 734.r>86.4172 Detroit Edison April 26,1999 NRC-99-0037 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington D C 20555-0001

References:

1) Fermi 2 NRC Docket No. 50-341 NRC License No. NPF-43

2) Fermi 2 Letter to NRC (NRC-93-0092) dated June 29,1998, " Issuance of Technical Requirements Manual Volume I to the Holders of the Updated Final Safety Analysis Report" l

3) Fermi 2 Letter to NRC (NRC-98-0156) dated October 16,1998, " Status of the Fermi 2 UFSAR Validation and other 50.54(f)

Response Initiatives"

Subject:

Submittal of Revision 9 to the Fermi 2 Updated Final Safety Analysis Report Pursuant to 10 CFR 50.71(e) and 10 CFR 50.4(b)(6), Detroit Edison hereby submits !

I Revision 9 to the Fermi 2 Updated Final Safety Analysis Report (UFSAR).

One signed original and ten additional copies of the UFSAR, Revision 9, are being submitted to the Document Control Desk. In addition, one copy will be submitted to Region III and one copy to the NRC Resident Inspector. Changes associated with '

Revision 9 are annotated by revision bars in the appropriate margin. All revised 3 pages are marked "REV 9 4/99" in the lower right-hand comer.

In accordance with 10 CFR 50.71(e) the information provided in this submittal describes the plant configuration through October 29,1998 as a minimum and reflects changes made since Revision 8 that were made under the provisions of 10 CFR 50.59. This revision also includes the correction of a number of discrepancies

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USNRC NRC-99-0037 l Page 2 that were identified during the UFSAR validation initiative. As discussed in Reference 3, the schedule for correcting the remaining discrepancies will be determined following the issuance of the final Regulatory Guide endorsing NEI 98-03. We understand that this guide is currently scheduled to be published in September 1999.

This submittal also includes a sununary description of the changes to the Quality Assurance Program. This summary (Enclosure 1) is being submitted to fulfill the requirements of 10 CFR 50.54(a)(3)(ii).

Enclosure 2 is the Safety Evaluation Summary Report containing a brief description of safety e.aluations performed for changes to plant design, procedures, tests, experiments, temporary modifications and the UFSAR. This report is being submitted to meet the 10 CFR 50.59(b)(2) requirement.

Detroit Edison revised Fermi 2 administrative programs and procedures in 1996 to be consistent with NEI's " Guideline for Managing NRC Commitments" Revision 2, dated December 19,1995. Consistent with these guidelines a Commitment Management Report (Enclosure 3) update is included which provides a brief summary of commitments that have been changed by Detroit Edison using these guidelines since the initial report submitted with UFSAR, Revision 8.

Enclosure 4 provides a summary of the changes that were made to Volume 1 of the Technical Requirements Manual (TRM) after May 27,1998 through October 29, 1998. Also included is an information copy of the TRM pages that were revised and issued during this period. This meets the Edison commitment included in Reference 2 above.

Should you have any questions or require additional information, please contact Mr. Norman K. Peterson of my staff at (734) 586-4258.

Sincerely, ,

/

Enclosures cc: A. J. Kugler A. Vegel NRC Resident Office Regional Administrator,RegionIll l

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USNRC

, NRC-99-0037 l Page 3 l

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I, DOUGLAS R. GIPSON, do hereby affirm that the foregoing statements are based on facts and circumstances which are true and accurate to the best of my knowledge and belief.-

DOUGLASR. GIPSON l Senior Vice President, Nuclear Generation 1

l On this M[FN day of d ._,1999 before me personally appeared Douglas R. Gipson, being first duly sworn and says that he executed the foregoing as his free act and deed.

l 4/ 44s -

'C Notary Public ROSALIE A. ARME1TA NOTARY PUBUC-MONRDE COUNTV,Mi MYCOMMISS10N EXPlRES10/11/09

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l ENCLOSURE I TO NRC-99-0037 DESCRIPTION OF CHANGES TO THE QUAL'TY ASSURANCE PROGRAM INCORPORATED IN REVISION 9 OF THE FERMI 2 UFSAR, SECTION 17.2 i

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l Enclosure 1 to NRC-99-0037 l Page 1 of 2 l

l DESCRIPTION OF CHANGES TO THE QUALITY ASSURANCE PROGRAM INCORPORATED IN REVISION 9 OF THE FERMI 2 UFSAR, SECTION 17.2 During the UFSAR Revision 9, changes were made to the Fermi 2 Quality Assurance Program described in Section 17.2 of the UFSAR. These changes were consistent with the requirements of 10CFR50.54 and continue to satisfy the criteria of Appendix B and the Safety Analysis Report for the Quality Assurance Program description commitments previously accepted by the NRC.

A description of these changes and the applicable Licensing Change Request (LCR) reference are provided below. j e LCR 96-090-UFS: Per Technical Specifications Amendment 113, the following sections were revised to relocate portions of Technical Specifications Section 6 to UFSAR Section 17.2:

Sections 17.2.1.7.1,17.2.1.7.2,17.2.1.7.3, and 17.2.18 were revised to incorporate the j relocation of the functions and responsibilities of Nuclear Safety Review Group (NSRG),

Onsite Review Organization (OSRO) and Independent Safety Engineering Group (ISEG).

Section 17.2.5 was revised to incorporate the relocation of technical review and control of procedures, review and approval process and temporary change process of procedures, and the Process Control Program.

Section 17.2.17 was revised to incorporate the relocation of record retention requirements.

. LCR 97-042-UFS Rev A: Sections 17.2.1.1,17.2.1.1.1,17.2.1.3,17.2.1.3.1 and Figure 17.2-1 were revised to reflect reporting changes for the Vice President - Nuclear Generation, added the Technical Manager position and deleted Assistant Vice President and Technical Manager position.

LCR 97-114-UFS: Section 17.2.1.3 and Figure 17.2-1 were revised to delete reference to the Supervisor, Turbine and associated responsibility as a result of the Turbine Group demobilization.

LCR 97-174-UFS: Sections 17.2.1.7.1.8,17.2.1.7.1.9,17.2.1.7.2.6,17.2.1.7.2.7, 17.2.5.1.2.1,17.2.5.1.2.2,17.2.5.2.1,17.2.5.2.2,17.2.5.2.3,17.2.17.4.1,17.2.17.4.2 and 17.2.17.4.3 were revised to make format corrections that were not included in LCR 96-090-1 UFS to be consistent with the UFSAR format.

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n l Enclosure I to NRC-99-0037 Page 2 of 2 e LCR 98-048-UFS Rev A: Sections 17.2.1.1,17.2.1.1.1,17.2.1.2,17.2.1.5,17.2.1.5.2, 17.2.1.7.1.1,17.2.1.7.1.2,17.2.1.7.1.6,17.2.1.7.1.8,17.2.1.7.3.4,17.2.5.2.1,17.2.5.2.2, 17.2.5.3.1,17.2.11,17.2.16,17.2.18.3 and Figure 17.2-1 were revised to reflect the change in titles of the Plant Manager to Assistant Vice President - Nuclear Operations and Nuclear Assessment Manager to Assistant Vice President - Nuclear Assessment. It was noted that while the new titles were in effect, the new titles were synonymous with the old titles with respect to their individual responsibilities. Corrected title of Technical Manager which was missed when title was changed in LCR 97-042-UFS Rev A.

. LCR 98-095-UFS: Sections 17.2.1,17.2.6,17.2.7,17.2.17 and Figure 17.2-1 were revised to reflect Corporate and Nuclear Generation Organization changes. Title of Chairman of the Board and Chief Executive Officer was changed to Chairman and Chief Executive Officer.

Described the Corporate and Fermi 2 reporting relat'.onships associated with the Senior Vice President - Nuclear Generation. Added the position of Director, Supply Chain Management Process.

. LCR 98-195-UFS: Sections 17.2.1.3,17.2.1.3.1,17.2.1.3.2,17.2.1.3.4,17.2.7 and Figure

. 17.2-1 were revised to change title of Superintendent of System Engineering to Director, I System Engineering. Added Director, Engineering Projects and described the position's function. Deleted Supervisor Modifications and Director, Nuclear Fuels and Reactor Engineering. Changed Supervisor, Procurement responsibility for issuance of purchase orders to Nuclear Generation and/or Supply Chain Management, t

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ENCLOSURE 2 TO NRC-99-0037 SAFETY EVALUATION

SUMMARY

REPORT (This is in a separate binder attached to NRC-99-0037 as Enclosure 2) l l

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k ENCLOSURE 3TO NRC-99-0037 COMMITMENT MANAGEMENT REPORT I

L Enclosure 3 to NRC-99-0037 Page1of12 Commitment Mananement Report In 1996 Fermi 2 administrative programs and procedures were revised to be consistent with NEl's " Guidelines for Managing NRC Commitments" Revision 2, dated December 19,1995.

. Fermi 2 began using 6e basic criteria included in the NEI process during the NEl-NRC Pilot Program for the Guidelines in 1995. These Guidelines discuss the need for a report to be submitted either annually or along with the FSAR updates required by 10 CFR 50.71(e). This Enclosure constitutes the update to Fermi 2 Commitment Management Report submitted initially with Revision 8 of the UFSAR.

The NEI process also provides for notifying the NRC of commitment changes when certain criteria are met. These criteria have been incorporated in Fermi 2 procedures for managing commitments. For example, a revised schedule for implementing commitments made in response to a Generic Letter would require specific and timely NRC notification. The purpose of this report is to provide a record of those commitment changes that did not require a notification at the time of the change.

The report consists of three tables as described below. Each table includes a brief statement of the commitment subject and origin. The changes being reported in these tables do not in any way affect or change commitments or descriptions included in the UFSAR. Furthermore, in many cases the only " change" being made is that the activity will no longer be tracked by Fermi 2 as a regulatory commitment. These two points are very important and are discussed funher in the following paragraphs.

This report involves pajy changes that have been made in the Fermi 2 commitment management program (referred to as the Regulatory Action Commitment and Tracking System or RACTS).

Some commitments identified in this report as being revised by this process may also be redundant to similar statements or licensing basis " commitments" included in the Fermi 2 UFSAR. Including a change in this report does Dqt, however, infer that the commitment or statement in the UFSAR has been revised. Application of the NEI Guidelines ensure that changes to such commitments in the UFSAR, including the Quality Assurance Program, would continue to be made and reported using the appropriate regulatory process (i.e. 50.59 or 50.54.).

Many of the " changes" being reported do not actually involve a change in the underlying activity or item that was the subject of the original commitment. The activity itself may be continued; I

however, Detroit Edison will no longer track the individual item as a regulatory commitment.

This action, in effect, " withdraws" or eliminates the original commitment. This practice is l

consistent with the NEI Guidelines that recognize that licensees need the flexibility to ch mge or eliminate commitments they determine are no longer necessary. One of the criteria suggested by the Guidelines as an acceptable basis for eliminating a commitment is when it has been " captured as part of an ongoing program or other administrative control that is subject to a revision review process." Commitment changes being reported are included in the following three tables:

i Enclosure 3 to NRC-99-0037 Page 2 of12 e TABLE 1: Comritments that were deleted from the Fermi 2 commitment tracking program because they are included in an ongoing program or procedure that is subject to a revision review process. Table 1 may also include commitments that were deleted from the tracking

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program because they were redundant to commitments in the UFSAR.

e TABLE 2: Commitments that were deleted from the Fermi 2 commitment tracking program for reasons other than those listed for Table 1.

TABLE 3: Commitments that were not deleted, but were revised in the commitment tracking program. A statement of the original commitment and reference is given along with a brief description of the revision.

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ENCLOSURE 4TO NRC-99-0037 l

SUMMARY

OF THE CHANGES MADE TO VOLUME 1 OF THE TECHNICAL REQUIREMENTS MANUAL AFTER MAY 27,1998 i THROUGH OCTOBER 29,1998 c

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\

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I

n Enclosure 4 to NRC-99-0037 Page 1 of 27

SUMMARY

OF TECHNICAL REOUIREMENTS MANUAL (TRM)

VOLUME I CHANGES On May 26,1998, a change was made to UFSAR Section 1.6, " Material Incorporated by Reference."

This change added Volume I of the Fermi 2 TRM as a document incorporated into the UFSAR by referencing it in Section 1.6.

On May 27,1998, Revision 19 of the Fermi 2 TRM Vol I was submitted to all holders of controlled copies of the TRM. The following is a summary of changes made to the TRM after May 27,1998 through October 29,1998.

Revision 20 Technical Specifications (TS) Amendment 115 relocated the following 6/10/98 requirements and their associated Bases from the TS to the UFSAR TS 3/4.3.7.2 - Seismic Monitoring Instrumentation TS 3/4.3.7.3 - Meteorological Monitoring Instrumentation TS 3/4.3.7.7 - Traversing In-Core Probe System TS 3/4.3.7.8 - Chlorine Detection System TS 3/4.3.7.10 - Loose Part Detection System Revision 21 Revised Table 3.3.7.2-1 to show one installed location (switchgear room) of the 6/16/98 passive seismic instrumentation in the RHR Building.

Revision 22 Made editorial correction to restore missing " delta" symbol to Table 3.3.2-3, items 8/l8/98 2.a and 2.c regarding Reactor Water Cleanup System isolation.

Revision 23 Corrected typographical errors in the Table of Contents and Table 3.8.4.3-1 " Motor 9/23/98 Operated Valves Thermal Overload Protection."

Revision 24 Added Core Operating Limits Report for Cycle 7 (Not part of the UFSAR).

10/8/98 Revision 25 Revised Table 3.3.1-2 to reflect changes to the Reactor Protection System response 10/9/98 times for the Average Power Range Monitors changed by a plant modification.

(EDP 27421)

Revision 26 Revised Table 3.3.3-3 to reflect .hanges to the Low Pressure Coolant Injection 10/13/98 Mode of RHR System response times for the Emergency Core Cooling System changed by a plant modification. (EDP 28886).

l The following pages are information only copies of the revised TRM pages for the above revisions, with the exception of Revision 24.

l

1 Encloswe 4 to NRC-99-0037 Page 2 0f 27 FERMI 2 - TECFNICAL REQUIREMENTS MANUAL I

TABLE OF SONTENTS - VOLUME Section and Title P.a92 .

l INTRODUCTION.......................................... 1 SECTION 1 DEFINITIONS TR 1.0 DEFINITIONS ............................... 1-1 3 J

SECTION 2 SAFETY LIMITS TR 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS .............................. .. 2-1 SECTION 3 APPLICABILITY TR 3/4.0 APPLICABILITY.................. .. .. . 3/4 0-1 SECTION 3.1 TR 3/4.3.1 REACTIVITY CONTROL SYST . ........ 3/4 1-1 SECTION 3.2 TR 3/4.3.2 POWER DISTRIBUTION MITS .......... 3/4 2-1 SECTION 3.3 TR 3/4.3 INSTRUMENTATION 1

TR 3/4.3.1

~

Reactor Pro ystem Instrumen ....................... 3/4 3-1 TR 3/4,3.2 Isolati tu on Instrumentation... 3/4 3-4 TR 3/4.3.3 Emergene ooling System Actuation Inst tat n....................... 3/4 3-8 TR 3/4.3.7.2 is nitoring Instrumentation.. 3/4 3-11 TR 3/4.3.7.3 o ogical Monitoring

' mentation ................... 3/4 3-15 TR 3/4.3.7. rsing In-Core Probe System..... 3/4 3-19 TR 3/4.3. orine Deteption System........... 3/4 3-21 TR 3/4 ose-Part Detection System......... 3/4 3-23 SECTIO TR EACTOR COOLANT SYSTEM.................. 3/4 4-1 S

5 EMERGENCY CORE COOLING SYSTEMS.......... 3/4 5-1 SE 3.6 3/4.6 CONTAINMENT SYSTEMS.....................

TR 3/4.6.1 Primary Containment...................

TR 3/4.6.2 Depressurization Systems..............

TR 3/4.6.3 Primary Containment Isolation Valves.. 3.6-1 l TR 3/4.6.4 Vacuum Hi.............................

TR 3/4.6.5 Secondary Containment.................

TR 3/4.3.6 Prir.ary Containment...................

l TRM Vol. I i REV 20 06/98 t

Enclosme 4 to NRC-99-0037

! Page 3 of 27 l FERMI 2 - TECHNICAL REQUIREMENTS MANUAL l

TABLE OF CONTENTS (Cont'd) - VOLUME 1 l Section and Title fagg l SECTION 3.7 TR 3/4.7 PLANT SYSTEMS........................... 3/4 7-1 TR 3/4.7.1 Service Water Systems.................

TR 3/4.7.2 Control Room Emergency Filtration System TR 3/4.7.3 Shore Barrier Protection..............

TR 3/4.7.4 Reactor Core Isolation Cooling Syste .

TR 3/4.7.5 Snubbers.......................... .

TR 3/4.7.6 Sealed Source Contamination...... .

i TR 3/4.7.9 Main Turbine Bypass System and Moisture Separator Reheater. . ..

TR 3/4.7.10 Reserved............... ..... .. ..

TR 3/4.7.11 Appendix R Alternative Shu Auxiliary Systems...... . ........

SECTION 3.8 '

TR 3/4.8 ELECTRICE SYSTEMS... ....... ..........

TR 3/4.8.1 AC Sources........ ...............

TR 3/4.8.2 DC Sources.... ..................

TR 3/4.8.3 Onsite Power u on Systems.....

TR 3/4.8.4 Electrical r Protective Devices - ated Valves Thermal oa rotection........... 3/4 8-1 ;

SECTION 3.9 l TR 3/4.9 REFUE NG TION..................... 3/4 9-1 .

TR 3/4.9.1 ode Switch...................

TR 3/4.9.2 entatFin.......................

TR 3/4.9. t 1 Rod Position..................

TR 3/4. e y Time............................ l TR 3/4. .5 munications........................

TR 3 Refueling Platform....................

. Crane Travel - Spent Fuel Storage Pool

.8 Water Level - Reactor Vessel ..........

. .9 Water Level - Spent Fuel Storage Pool.

.9.10 Control Rod Removal...................

4.9.11 Residual Heat Removal.................

SECT ON 3.10 TR 3/4.10 SPECIAL TEST EXCEPTIONS................ 3/4 10-1 TR 3/4.10.1 Primary Containment Integrity........

TR 3/4.10.3 Shutdown Margin Demonstrations.......

TR 3/4.10.4 Recirculation Loops..................

TR 3/4.10.5 Deleted..............................

TR 3/4.10.6 Training Startups....................

TRM Vol. I 11 REV 20 06/98 l

Enclosure 4 to NRC-99-0037 Page 4 of 27 FERMI _2.- TECHNICAL REOUIREMENTS MANUAL TABLE OF CONTENTS (Cont'd) - VOLUME 1 Section and Title Eg2.%

SECTION 3.11 TR 3/4.11 RADIOACTIVE EFFLUENTS.................. 3/4 11-1 TR 3/4.11.1 Liquid Effluents.....................

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SECTION 3.12 TR 3/4.12 DELETED ............................. ..

SECTION 5 DESIGN FEATURES TR 5.0 DESIGN FEATURES................... ..... 5-1 TR 5.1 SITE............................. .. . ..

TR 5.2 CONTAINMENT ................ . .........

TR 5.3 REACTOR CORE............... . .........

TR 5.4 REACTOR COOLANT SYSTE . ..................

TR 5.5 METEOROLOGICAL TOW N.............

TR 5.6 FUEL STORAGE.. . .. ...................

TR 5.7 COMPONENT CO RANSIENT LIMIT.......

SECTION 6 ADMINIS ROLS TR 6.0 ADMINI RA ONTROLS ................... 6-1 TR 6.1 RES ............................

l TR 6.2 Z ION ..............................

TR 6.2{ 1 3 site and Onsite Organizations........

TR Dnit Staff..............................

. Independent Safety Engineering Group....

.4 Shift Technical Advisor.................

UNI *. S7AFF QUALIFICATIONS.................

6.5 REVIEW AND AUDIT................. ........

TR 6.5.1 Onsite Review Organization (OSRO) .......

TR 6.5.2 Nuclear Safety Review Group (NSRG) . . . . . .

TR 6.5.3 Technical Review and Control............

TR 6.6 REPORSECTIONLE EVENT ACTION...............

TR 6.7 SAFETY LIMIT VIOLATION....................

TR 6.8 PROCEDURES AND PROGRAMS...................

TRM Vol. I iii REV 20 06/98 l t

Enclostre 4 to NRC-99-0037 PaE2 5 of 27 FERMI 2 - TECHNICAL REQUIREMENTS MANUAL TABLE _OF CONTENTS (Cont'd) - VOLUME 1 Section and Title.....................................Eggg TR 6.9 REPORTING REQUIREMENTS.......................

TR 6.9.1 Routine Reports.........................

TR 6.9.2 Special Reports..........................

TR 6.9.3 Core Operating Limits Report............

TR 6.10 RECORD RETENTION.........................

TR 6.11 RADIATION PROTECTION PROGRAM....... .

TR 6.12 HIGH RADIATION AREA............. ... .

TR 6.13 PROCESS CONTROL PROGRAM...... . ...

TR 6.14 OFFSITE DOSE CALCULATION J . .......

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l TRM Vol. I iv REV 20 06/98 l

Enclosure 4 to i NRC-99 0037 l l

Page 6 of 27 FERMI 2 TECHNICAL REQUIREMENTS MANUAL TABLE OF CONTENTS (CONT'D) - VOLUME 1 LIST OF TABLES TRM Table Number Title Eaca 1.1 Surveillance Frequency Notation........... 1-3 1

1.2 Operational Conditions................. .. 1-4 l 3.3.1-2 Reactor Protection System Response Times ............................. ..... 3/4 3-2 3.3.2-3 Isolation Actuation System Instrumentation Response Time. . .... 3/4 3-5 3.3.3-3 Emergency Core Cooling Systd m nse Times...................... . . .......... 3/4 3-9 .

I 3.3.7.2-1 Seismic Monitoring I ' mentation........ 3/4 3-12 i

4.3.7.2-1 Seicmic Monitorin mentation Surveillance Re t ................. 3/4 3-13 3.3.7.3-1 Meteorologi '. ng Instrumentation. 3/4 3-16 1

4.3.7.3-1 Meteorolo ic toring Instrumentation Surveilla Re irements ................. 3/4 3-17 3.6.3-1 Prim n inment Isolation Valves...... 3/4 6-2 3.8.4.3-1 ated Valves Thermal Overload

- n ................................ 3/4 8-2 l

{

TRM Vol. I y REV 20 06/98 k

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Enclosure 4 to NRC-99-0037 Page 7 of 27 '

3/4.3 INSTRUMENTATION 3/4.3.7.2 SEISMIC MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.7.2 The seismic monitoring instrumentation shown in TRM Table 3.3.7.2-1 shall be OPERABLE.

APPLICABILITY: At all times.

ACTION:

a. With one or more of the abe- re smic monitoring instruments inopera s re the inoperable instrument to OPE s within the next 30 days.

b. With the above required ON and associated completion time not me , ate a corrective action program document if not already been initiated.

SURVEILLANCE REQUIREM 4.3.7.2.1 Each of he v

yrequ ired seismic monitoring in W ruments shall de trated OPERABLE by the performance of the CHANNEL CHEC FUNCTIONAL TEST and CHANNEL CALIBRATION ;

operations at e neies shown in TRM Table 4.3.7.2-1. l 4.3.7.2.2 a e above required seismic monitoring instrumen ed during a seismic event greater than or equal to 0.01 e restored to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and a RATION performed within 5 days following the sei . Data shall be retrieved from actuated instruments a d to determine the magnitude of the vibratory ground Special Report shall be prepared and submitted to the alon pursuant to Technical Specification 6.9.2 within 10 d scribing the magnitude, frequency spectrum, and resultant eff e upon unit features important to safety.

TRM Vol. I 3/4 3-11 REV 20 06/98

Encice,t.re 4 to NRC-99-0037 Page 8 of 27 l

z TRM TABLE 3 . 3 . 7 . 2 -1 l l

l SEISMIC MONITORING INSTRUMENTATION '

I MINIMUM MEASUREMENT INSTRUMENTS INSTRUMENTS AND SENSOR LOCATIONS RANGE OPERABLE 1

1. Active Triaxial System

a. Active Triaxial Accelerometers

HPCI Room 1 1

2) Base of RPV Pedestal, In Drywe 1

b. Active Seismic Recording System *

1) Relay Room, Auxiliary B ding NA 1**

c. Active seismic Playback m

1) Relay Room, Auxi B f ding NA NA 2 2. Passive Triaxial Peak ok orders

a. HPCI Room *** 1

b. Relay Room ux i Building *** 1

c. Refue actor Building *** 1

d. Dies ator Room, RHR Complex *** 1

e. ,, RHR Complex *** 1

. oling Tower, RHR Complex *** 1 s

I uiling seismic trigger.

- ith reactor control room annunciation.

- - Each passive accelerometer has 12 reeds, each monitoring a different frequency. The frequencies correspond to varying accelerations.

The widest range is t 90 g.

TRM Vol. I 3/4 3-12 REV 20 06/98 l

Enclosure 4 to NRC-99-0037 Page 9 of 27 TRM TABLE 4.3.7.2-1 SEISMIC MONITORING INSTRUMENTATIC?J SURVEIT.TANCE REOUIREMENTS CHAlmEL CHANNEL FUNCTIONAL CHANNEL INSTRUMENTS AND SENSOR LOCATIONS CHECK TEST CALIBRATION

1. Active Triaxial System

a. Active Triaxial Accelerometers

1) HPCI Room NA SA ' R

2) Base of RPV Pedestal, In Drywell NA R

b. Active Seismic Recording

System *

1) Relay Room, Auxiliary Building ** M(a) SA R

c. Active Seismic Playba k m

1) Relay Room, '

1 Building M SA R

2. Passive Triaxial Pe hoc .

Recorders

a. HPCI Ro .. NA NA R

b. Rel 7,, uxiliary B NA NA R

c. el Floor, Reactor i ng NA NA R esel Generator Room, RHR Complex NA NA R

. Pump Room, RHR Complex NA NA R

f. Cooling Tower, RHR Complex NA NA R

Including seismic trigger.

- With reactor control room annunci& tion.

(a)Except seismic trigger.

TRM Vol. I 3/4 3 M,3 REV 20 06/98

Enclosure 4 to NRC-99-0037 Page 10 of 27 l

i INSTRUMENTATION 1

j BASES 3/4.3.7.2 SEISMIC MONITORING INSTRUMENTATION The OPERABILITY of the seismic monitoring instrumentation ensures that sufficient capability is available to promptly determine the magnitude of a seismic event and evaluate the response of those features important to safety. This capability is required to permit comparison of the measured re nse to that used in the design basis for the unit. This inst tation is consistent with the recommendations of Regulato Gul .12,

" Instrumentation for Earthquakes," April 1974 Entry into Action b and the initiation of a c ve action program document will cause a determinat r rtability to the commission in accorduace with the re s of 10 CFR 50.72 and 10 CFR 50.73.

I l

0 TRM Vol. I 3/4 3-14 REV 20 06/98

F i

Enclosure 4 to NRC-99-0037 Page 11 of 27 3/4.3 INSTRUMENTATION 3/4.3.7.3 METEOROLOGICAL MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.7.3 The meteorological monitoring instrumentation channels shown in TRM Table 3.3.7.3-1 shall be OPERABLE.

APPLICABILITY: At all times.

ACTION:

a. With less than the required channels ERh3 in TRM Table 3.3.7.3-1, restore the inope 1 h.)nnelto OPERABLE status within the next 7

b. With the above required ACTION ciated completion time not met, initi orrective action program document if one h not ady been initiated.

SURVEILLANCE REQUIREMENTS Ag w

4.3.7.3 Each of the ab q ed meteorological monitoring )

instrumentation chann is e demonstrated OPERABLE by the performance of the L CK and CHANNEL CALIBRATION operations at the e s shown in TRM Table 4.3.7.3-1.

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TRM Vol. I 3/4 3-15 REV 20 06/98

l Enclosure 4 to NRC-99-0037 l Page 12 of 27 l

l TRM TABLE 3.3.7.3-1 METEOROLOGICAL MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE

a. Wind Speed l

1. Elev. 10. meters 1

2. Elev. 60 meters 1

b. Wind Direction

1. Elev. 10 meters 1

2. Elev. 60 meters 1

c. Air Temperature Differen

1. Elev. 10/60 met 1 i

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1 TRM Vol. I 3/4 3-16 REV 20 06/98

F l l Enclosure 4 to NRC-99-0037 Page 13 of 27 TRM TABLE 4 . 3 . 7. 3 -1 METEOROLOGICAL MMITORING INSTRUMENTATION SURVEIT.TANCE REOUIREMENTS CHANNEL CHANNEL I INSTRUMENT CHECK CALIBRATION

a. Wind Speed

1. Elev. 10 meters D SA

2. Elev. 60 meters D A

b. Wind Direction

1. Elev. 10 meters SA

2. Elev. 60 meters SA

c. Air Temperature Difference

1. Elev. 10/60 meters D SA l l

h l

l I

TRM Vol. I 3/4 3-17 REV 20 06/98

1 to NRC-99-0037 Page 14 of 27 INSTRUMENTATION {

BASES 3/4.3.7.3 METEOROLOGICAL MONITORING INSTRUMENTATION The OPERABILITY of the meteorological monitoring instrumentation ensures that sufficient meteorological data are available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere. This capability is re ired to evaluate the need for initiating protective measu o protect the health and safety of the public. This inst men on is consistent with the recommendations of Regulat 1.23, "Onsite Meteorological Programs," February,1 .

Guq>d Entry into Action b and the initiation o r tive action program document will cause a determinat portability to the commission in accordance with the re ents of 10 CFR 50.72 and 10 CFR 50.73.

(i:5) l l

i I

+1 TRM Vol. I 3/4 3-18 REV 20 06/98

Enclostre 4 to NRC-99-0037 Page l5 of 27 3 /4 . 3 INSTRUMENTATION 3/4.3.7.7 TRAVERSING IN-CORE PROBE SYSTEM l LIMITING CONDITION FOR OPERATION l 3.3.7.7 The traversing in-core probe system shall be OPERABLE with:

! a. Five movable detectors, drives and reado equipment to map the core, and

b. Indexing equipment to allow all fiv e s to be calibrated in a common location.

APPLICABILITY: When the traversing in-c be is used for:

a. Recalibration of the LPRM dete , and

! b.* Monitoring the APLHGR, MCPR, or MFLPD.

ACTION:

With tho, traversing in-cor # stem inoperable, suspend use of the system for the ab , cable monitoring or calibration functions.

SURVEILLANCE REQR 4.3.7.7 Th g in-core probe system shall be demonstrated OPERABLE ing each of the above required detector outputs w hours prior to use when required for the LPRM calibr ion.

l

Only the detector (s) in the required measurement location (s) are required to be OPERABLE.

TRM Vol. I 3/4 3-19 REV 20 06/98

l Enclosure 4 to NRC-99-0037 Page 16 of 27 INSTRUMENTATION BASES 3/4.3.7.7 TRAVERSING IN-CORE PROBE SYSTEM The OPERABILITY of the traversing in-core probe system with the specified minimum complement of equipment ensures that the measurements obtained from use of this equipment accurately represent the spatial neutron flux distribution of the reactor core.

The TIP system OPERABILITY is demonstrated :py no izing all probes (i.e. , detectors) prior to performing a ibration function. Monitoring core thermal limits may tilizing individual detectors to monitor selected ar reactor core, thus all detectors may not be requi OPERABLE. The OPERABILITY of individual detectors to b r monitoring is demonstrated by comparing the detector (s) t with data obtained during the previous LPRM ca ibrat O

TRM Vol. I 3/4 3-20 REV 20 06/98

Enclosure 4 to NRC-99-0037 Page 17 of 27 3/4.3 INSTRUMENTATION 3/4.3.7.8 CHLORINE DETECTION SYSTEM LIMITING CONDITION FOR OPERATION 3.3.7.8 Two independent chlorine detectors shall be OPERABLE with their trip setpoints adjusted to actuate at chlorine concentration of less than or equal to 5 ppm.

APPLICABILITY: All OPERATIONAL CONDITIONS.

ACTION:

a. With one chlorine detector inopera , ore the inoperable detector to OPERABLE hin 7 days or, within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , i e d maintain isolation of all control room v intakes by placing the HVAC system in th 1 lae mode of operation.

I

b. With both chlorine det inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months i initiate and mainta' a n of all control room l emergency intakes b '. the HVAC system in the l chlorine mode of .

l SURVEILLANCE REQUIMME 4.3.7.8 Each o e required chlorine detectors shall be demonstrated y performance of a:

a. . CTIONAL TEST at least once per 31 days, and b EL CALIBRATION at least once per 18 months.

1 TRM Vol. I 3/4 3-21 REV 20 06/98 i

l

e z

Enclosure 4 to l

NRC-99-0037 Page 18 of 27 INSTRUMENTATION BASES 3/4.3.7.8 CHLORINE DETECTION SYSTEM The OPERABILITY of the chlorine detection system ensures that i an accidental chlorine release will be detected promptly and the !

necessary protective actions will be automatically initiated to provide protection for control room personnel. Upon detection of a high concentration of chlorine, the control room Anergency ventilation system will automatically be placed i e chlorine mode of operation to provide the required prote tio he detection system < equired by this Technical Re is consistent with the recommendations of Regul e 1. 95,

" Protection of Nuclear Power Plant Control ators against an Accidental Chlorine Release", Revisi a ry, 1977. l l

i

}

TRM Vol. I 3/4 3-22 REV 20 06/98

1 l

Enclosure 4 to NRC-99-0037 Page 19 of 27 3/4.3 INSTRUMENTATION 3/4.3.7.10 LOOSE-PART DETECTION SYSTEM LIMITING CONDITION FOR OPERATION 3.3.7.10 The loose-part detection system shall be OPERABLE.

APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2.

ACTION:

a. With one or more loose-part detection ys hannels inoperable, restorc the inoperable c e OPERABLE status within the next 30 days.

b. With the above required ACTION iated completion time not met, init . rective action program document if one has no already initiated.

SURVEILLANCE REQUIREMENTS 4.3.7.10 Each channel o -part detection system shall be demonstrated QPERABLE b fo nce of a:

a. CHANNEL CHE t 1 st once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ,

b. CHANNE T AL TEST at least once per 31 days, and

c. ' RATION at least once per 18 months.

t TRM Vol. I 3/4 3-23 REV 20 06/98

Enclosure 4 to NRC-99-0037 Page 20 of 27

)

INSTRUMENTATION BASES 3/4.3.7.10 LOOSE-PART DETECTION SYSTEM The OPERABILITY of the loose-part detection system ensures that sufficient capability is available to detect loose metallic pari.s in the primary system and avoid or mitigate damage to primary system components. The allowable out-of-service times and

, surveillance requirements are consistent with the r ommendations of Regulatory Guide 1.133, " Loose-Part Detection am for the Primary System of Light-Water-Cooled Reactors," ay .

Entry into Action b and the initiation of a r i action program document will cause a determinatio p tability to the commission in accordance with the 'r nts of 10 CFR 50.72 and 10 CFR 50.73.

O TRM Vol. I 3/4 3-24 REV 20 06/98

I Enclosure 4 to I

NRC-99-0037 Page 21 of 27 I

l TRM TABLE 1. 3 . "7 . 2 -1 SEISMIC MONITORING INSTRUMENTATION MINIMUM.

MEASUREMENT INSTRUMENTS l INSTRUMENTS AND SENSOR LOCATIONS RANGE OPERABLE I

1. Active Triaxial System

a. Active Triaxial Accelerometers

1) HPCI Room 1 1

2) Base of RPV Pedestal, In Dryw t 1

b. Active Seismic Recording System *

1) Relay Room. Auxiliary ding NA 1**

i

c. Active Seismic Playbac m i

1) Relay Room, A . ilding NA NA i

2. Passive Triaxial Pea c. corders I a. HPCI Room *** 1 1

b. Relay Roo A 1 ry Building *** 1 l c. Refue .eactor Building *** 1 l d. Die rator Room, RHR Ccmplex *** 1

e. wi ar Room, RHR Complex *** 1 i Coo ing Tower, RHR Complex *** 1 Tiding seismic trigger.

l ich reactor control room annunciation.

l ***Each passive accelerometer has 12 reeds, each monitoring a different frequency. Tae frequencies correspond to varying accelerations.

. The widest range is ; 90 g.

TRM Vol. I 3/4 3-12 REV 21 06/98

E Enclosure 4 to NRC-99-0037 Page 22 of 27 1

TRM - TABLE 3.3.2-3 i

(UFSAR TABLE 7.3-12)

ISOLATION ACTJATION SYSTEM INSTRUMENTATION RESPO'TSE TIME TRIP "JNCTION RESPONSE OTME (Seconds)

1. PRIMARY CONTATNMENT ISOLATION

a. Reactor Vessel Low Water Level

1) Level 3 NA

2) Level 2 NA

3) Level 1 11.0*"

b. Drywell Pressure - High NA

c. Main Steam Line

1) Radiation - High NA

2) Pressure - Low NA

3) Flow - High 10.5*"

d. Main Steam Line Tunnel Tem ature - High NA

e. Condenser Pressure - Hig NA

f. Turbine Bldg. Area Te re High NA

g. Deleted

h. Manual Initiatien NA

2. REACTOR WATER CT SOLATION

a. A Flow - gh NA l

b. Heat Exc e P . /High Energy Piping Area e - High NA r/ Pump / Phase Separator

c. Hea

" ation Temperature AT - High NA \

d. 'n -.ation NA

e. Vessel Low Water Level - Level 2 NA ed al Initiation NA

. 10R CORE ISOLATION COOLING SYSTEM ISOLATION

. RCIC Steam Line Flow - High NA

b. RCIC Steam Supply Pressure - Low NA

c. RCIC Turbine Exhaust Diaphragm Pressure - High NA

d. RCIC Equipment Room Temperature - High NA

e. Manual Initiation NA TRM Vol. .I 3/4 3-5 REV 22 08/98 1

1 p

i Enclosure 4 to NRC-99-0037 Page 23 of 27 ,,,wr 2 - m s sr. e n - a wa=rtr.

TABLE OF CONTENTS - VOLUME 1 l

-~see-icn and Title p.agg ,

I INTRODUCTION .......................................... 1 l

i SECTION 1 DEFINITIONS TR 1.0 DEFINITIONS............................... 1-1 SECTION 2 SAFETY LIMITS TR 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS ............................. ... 2-1 SECTION 3 APPLICABILITY l TR 3/4.0 APPLICABILITY................. ... . . 3/4 0-1 1 SECTION 3.1 TR 3/4.1 REACTIVITY CONTROL SYSTEM ... ...... 3/4 1-1 l SECTION 3.2 TR 3/4.2 POWER DISTRIBUTION L ITS ........... 3/4 2-1 l l

l SECTION 3.3 TR 3/4.3 INSTRUMENTATION TR 3/4.3.1 Reactor Pr e ystem l Instrume ..................... 3/4 3-1 TR 3/4.3.2 Isolat t ion Instrumentation... 3/4 3-4 ,

TR 3/4.3.3 Emerge r Cooling System Actuation !

Inst ent on....................... .4 3-8 TR 3/4.3.7.2 ei onitoring Instrumentation.. 3/4 3-11 TR 3/4.3.7.3 te r ogical Monitoring rumentation................... 3/4 3-15 TR 3/4.3.7 ersing In-Core Probe System..... 3/4 3-19 TR 3/4.3 . . orine Detection System........... 3/4 3-21 TR 3/ ' uoose-Part Detection System......... 3/4 3-23 SECTIO 3 . REACTOR COOLANT SYSTEM.................. 3/4 4-1 S 5

.5 EMERGENCY CORE COOLING SYSTEMS.......... 3/4 5-1 S N 3.6 3/4.6 CONTAINMENT SYSTEMS.....................

TR 3/4.6.1 Primary Containment...................

TR 3/4.6.2 Depressurization Systems..............

TR 3/4.6.3 Primary Containment Isolation Valves . 3.6-1 l TR 3/4.6.4 Vacuum H1.............................

l TR 3/4.6.5 Secondary Containment...... ..........

TR 3/4.3.6 Primary Containment...................

TRM Vol. I i REV 23 09/98

l Enclosure 4 to NRC-99-0037 Page 24 of 27 FERMI 2 - TECENICAL REOtTIREMENTS M&BUAL TABLE OF CONTENTS (Cent'd) - VOLUME 1

- ~Shet' ion and Tit 1e F.Agt SECTION 3.11 TR 3/4.11 RADIOACTIVE EFFLUENTS.................. 3/4 11-1 TR 3/4.11.1 Liquid Effluents.....................

SECTION 3.12 TR 3/4.12 DELETED................................

SECTION 5 DESIGN FEATURES TR 5.0 DESIGN FEATURES.................. ..... 5-1 TR 5.1 SITE.......................... . . .. ...

TR 5.2 CONTAINMENT............... . ... ......

TR 5.3 REACTOR CORE.............. . ...........

TR 5.4 REACTOR COOLANT SYS ...................

TR 5.5 METEOROLOGICAL TO ION.............

TR 5.6 FUEL STORAGE. . . .. ....................

TR 5.7 COMPONENT C TRANSIENT LIMIT.......

SECTION 6 ADMINIS M IVE NTROLS TR 6.0 ADMIN A CONTROLS................... 6-1 TR 6.1 RE I TY............................

TR 6.2 R i TION..............................

TR 6. .. f sice and Onsice Organizations........

TR 2 Unit Staff..............................

Independent Safety Engineering Group....

.4 Shift Technical Advisor.................

UNIT STAFF QUALIFICATIONS .................

6.5 REVIEW AND AUDIT..........................

TR 6.5.1 Onsite Review Organization (OSRO) .......

TR 6.5.2 Nuclear Safety Review Group (NSRG) ......

TR 6.5.3 Technical Review and Control............

TR 6.6 REPORTABLE EVENT ACTION................... l TR 6.7 SAFETY LIMIT VIOLATION.............. .....

TR G.8 PROCEDURES AND PROGRAMS...................

TRM Vol. I iii REV 23 9/98

p Enclosure 4 to NRC-99-0037 -

Page 25 of 27

- I_BM - TABLE 3.8.4.3-1 (Continued) _

MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION

~

_ SYSTEM (S) -

VALVE NUMBER AFFECTED t

12.

~

DELETED l

13.

~~

P4400-F601A Emergency Equipment Cooling Water i (EECW)

-- ~

P4400-F601B EECW P4400-F602A BBCW S4400-F602B EECW ;

P4400-F603A BECW P4400-F603B EECW P4400-F604 EECW P4400-F605A EECW P4400-F605B EECW _

P4400-F606A EECW P4400-F60GB EECW P4400-F607A EECW P4400-F607B EECW P4400-F608 E P4400-F613 P4400-FG14 P4400-F615 P4400-F616 /\

g E

14. P5000-F603 Compressed Air System P5000-F604 Compressed Air System

15. T4804-F60 Containment Atmosphere Control System T4804- Containment Atmosphere Cor trol System T4804- Containment Atmosphere Control System T48 Containment Atmosphere Control System T Containment Atmosphere Control System 3B Containment Atmosphere Control System 04A Containment Atmosphere Control System

-F604B Containment Atmosphere Control System

-F605A Containment Atmosphere Control System 04-F605B Containment Atmosphere Control System 4804-F606A Containment Atmosphere Control System T4804-F606B Containment Atmosphere Control System T4803-F601 Containment Atmosphere Control System T4803-F602 Containment Atmosphere Control System

16. T4901-F601 Primary Containment Pneumatic Supply System T4901-F602 Primary Containment Pneumatic Supply System i

TRM Vol. I 3/4 8-5 REV 23 9/98 to NRC-99-0037 Page 26 of 27 TRM - TABLE 3.3.1-2 (UFSAR TABLE 7.2-4)

REACTOR PROTECTION SYSTEM RESPONSE TIMES FUNCTIONAL UNIT WWRPONSE TIME fSeconda)

1. Intermediate Range Monitors:

a. Neutron Flux - High

b. Inoperative

2. Average Power Range Monitor *:

a. Neutron Flux - Upscale, Setdown

b. Simulated Thermal Power - Upscale A

c. Neutron Flux - Upscale HA

d. Inoperative NA

e. 2-out-of-4 Trip Voters 10.05*

3. Reactor Vessel Steam Dome Pres agh 1 0.55'

4. Reactor Vessel Low Water Levt '

ve 3 1 1.05'

5. Main Steam Line Isolation Vai e sure 1 0.06

6. Main Steam Line Radiatior NA

7. Drywell Pressure - Hig NA B. Scram Discharge Vol r ~evel - High

a. Float Switch NA

b. Level Trans tt NA

9. Turbine Stop osure s 0.06

10. Turbine Co o Fast Closure s 0.0B***

11. Reactor e wi Shutdown Position NA

12. Manual NA

13. Delet d

etectors, APRM channel and 2-out-of-4 Trip Voter digital e onics are exempt from response time testing. Response time be measured from activation of the 2-out-of-4 Trip voter output ay.

- - Measured from deenergization of K-37 relay which inputs the turbine control valve closure signal to the RPS.

The sensor response time need not be measured and may be assumed to be the design sensor response time. Prior to return to service of a new transmitter or following refurbishment of a transmitter (e.g.,

sensor cell or variable damping components), a hydraulic response time test will be performed to determine an initial sensor-specific response time value.

TRM Vol. I 3/4 3-2 REV 25 10/98

r 1 Enclosure 4 to NRC-99-0037 .

Page 27 of 27 TRM - Tant.r 3 , 3 , 3 3 (UFSAR TAnts 7,3 11)

EMERGENCY CORE COOLING SYSTEM RESPONSE TIMES TRIP. FUNCTION JtESPONSE TIME (Seconds)

1. CORE SPRAY SYSTEM

a. Reactor Vessel Low Water Level - Level 1 1 30**

b. Drywell Pressure - High 1 30**

c. Reactor Steam Dome Pressure - Low NA*

d. Manual Initiation MA

2. LOW Parentar COOLANT TMJECTION MODE OF RHR sisi ,'

a. Reactor Vessel Low Water Level - Level 1 1 72**

b. Drywell Pressure - High 1 72**

c. Reactor Steam Dome Pressure - Low NA*

d. Reactor Vessel Low Water Level - Ley NA

e. Reactor Steam Dome Pressure - Low NA

f. Riser Differential Pressure - Higd NA

g. Recirculation Pump Differential Pr - NA High

h. Manual Initiation NA

3. HIGH PRESSURE COOLANT TNJECT N

a. Reactor Vessel Low W - Level 2 1 30**

b. Drywell Pressure - NA

c. Condensate Stora vel - Low NA

d. Reactor vessel Le - High, Level 8 NA

e. Suppression P 1 Level - High NA

f. Manual Initia NA

4. AUTOMATIC DEPR TR ON SYSTEM

a. React cw Water Level - Level 1 NA

b. D r re - High NA

c. ADS - NA

d. Pump Discharge Pressure - High NA

e. Mode Pump Discharge Pressure - High NA f t vessel Low Water Level - Level 3 NA Initiation NA

. rywell Pressure - High Bypass Timer NA ,

ual Inhibit NA ]

1 S OF PONRR '

7 l

a. 4.15 kV Baergency Bus Undervoltage (Loss )

of Voltage) MA

b. 4.15 kV Emergency Bus Undervoltage (Degraded Voltage) NA These are permissive signals only. They do not activate ECCS initiation.

- ECCS actuation instrumentation response time need not be measured and may be assumed to be the design instrumentation response time. Prior to return to service of a new transmitter or following refurbishment of a transmitter (e.g. , sensor cell or variable damping components),

a hydraulic response time test will be performed to determine an initial sensor-specific response time value.

TRM Vol. I 3/4 3-9 REV 26 10/98 o

NRC-99-0037, Forwards Rev 9 to Fermi 2 Ufsar,Per 10CFR50.71(e) & 10CFR50.4(b)(6).Summary of Changes to QA Program & Vol 1 of Technical Requirements Manual,Encl

Text

References:

Subject:

SUMMARY

SUMMARY

SUMMARY

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