ML20006A697

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Amend 49 to License NPF-43,revising Tech Spec Provisions to Allow Primary & Secondary Containment Penetrations Be Verified Closed Each Cold Shutdown Rather than Every 31 Days
ML20006A697
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 01/18/1990
From: Thoma J
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20006A698 List:
References
NUDOCS 9001300036
Download: ML20006A697 (14)
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Text

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UNITED $TATES I

NUCLEAR REGULATORY COMMISSION o-5 E

WASHING ton, D. C. 20566 i

%,... + $

t DETROIT EDISON COMPANY WOLVEkINE POWER SUPPLY COOPERATIVE, INCORPORATED i

DOCKET NO. 50-341 FERMI-2

_ AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 49 License No NPF-43 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by the Detroit Edison Company (the licensee) dated January 26, 1988, as supplemented by letters dated August 24, 1988, and May 31, 1989 complies with the stahdards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Commission's rules and regulations set forth in 10 CFR Chapter I; l

B.

The facility will operate in conformity with the application, the provisions of the Act and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

I l

2.

Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment and paragraph i

2.C.(2) of Facility Operating License No. NPF-43 is hereby amended to read as follows:

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 49, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.

Deco shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

9001300036 900118 FF;DR ADOCK 05000341 l

FDC i

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3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION h

ohn O. Thoma,. Acting Director Project Directorate 111-1 Division of Reactor Projects - III, IV, V & Special Projects Office of Nuclear Reactor Regulation

Attachment:

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Changes to the Technical Specifications Date of Issuance: January 18, 1990 k

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t ATTACPMENT TO LICENSE AMENDMENT NO. 4g, FACILITY OPERATING LICENSE NO. NPF-43 DOCKET NO. 50-341 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain a vertical line indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.

I RFM0VE INSERT xiii*

xiii*

xiv xiv xxiii*

xxiii*

xxiv xxiv 3/4 6.1 3/4 6-1 3/4 6-la 3/4 6-lb 3/4 6-2*

3/4 6-2*

3/4 6-51a 3/4 6-51a B 3/4 6-1 B 3/4 6-1 B 3/4 6-la t

l l

l l

  • 0verleaf page provided to maintain document completeness. No changes contained on these pages w

INDEX i

I BASES SECTION PAGE INSTRUMENTATION (Continued)

MONITORING INSTRUMENTATION (Continued)

Meteorological Monitoring Instrumentation.......

B 3/4 3-4 Remote Shutdown System Instrumentation and l

Controls........................................

B 3/4 3-4 l

Accident Monitoring Instrumentation.............

B 3/4 3-4 Source Range Monitors...........................

B 3/4 3-4 Traversing In-Core Probe System.................

B 3/4 3 4 Chlorine Detection System.......................

B 3/4 3-5 0ELETED.........................................

B 3/4 3-5 Loose-Part Detection System.....................

B 3/4 3-5 i

Radioactive Liquid Effluent Monitoring Instrumentation.................................

B 3/4 3-5 l

Radioactive Gaseous Effluent Monitoring l

Instrumentation.................................

B 3/4 3-6 3/4.3.8 TURBINE OVERSPEED PROTECTION SYSTEM.............

B 3/4 3-6 i

3/4.3.9 FEEDWATER/ MAIN TURBINE TRIP SYSTEMS ACTUATION INSTRUMENTATION.................................

B 3/4 3-6 3/4.3.10 APPENDIX R ALTERNATIVE SHUTDOWN INSTRUMENTATION j

AND CONTR0LS....................................

B 3/4 3-8 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM............................

B 3/4 41 3/4.4.2 SAFET\\/ RELIEF VALVES............................

B 3/4 41 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems.......................

B 3/4 4-2 Operational Leakage.............................

B 3/4 4-2 3/4.4.4 CHEMISTRY.......................................

B 3/4 4-2 3/4.4.5 SPECIFIC ACTIVITY...............................

B 3/4 4-3 3/4.4.6 PRESSURE / TEMPERATURE LIMITS.....................

B 3/4 4-4 3/4.4.7 MAIN STEAM LINE ISOLATION VALVES................

B 3/4 4-5 3/4.4.8 STRUCTURAL INTEGRITY............................

B 3/4 4-5 3/4.4.9 RESIOUAL HEAT REM 0 VAL...........................

B 3/4 4-5 FERMI - UNIT 2 xiii Amendment No. 49

INDEX BASES SECTION PAGE 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1/2 ECCS - OPERATING and SHUTD0WN...........,........ B 3/4 5-1 3/4.5.3 SUPPRESSION CHAMBER..............................

B 3/4 5-2 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT Primary Contai nment Integri ty.................... B 3/4 6-1 Primary Contai nment Leakage...................... B 3/4 6-1 Primary Containment Ai r Locks.................... B 3/4 6-la l MSIV Leakage Control System...................... B 3/4 6-2 Primary Containment Structural Integrity......... B 3/4 6-2 l

Drywell and Suppression Chamber Internal l

Pressure.......................................

B 3/4 6-2 l

Drywell Average Ai r Temperature.................. B 3/4 6-2 Drywell and Suppression Chamber Purge System..... B 3/4 6-2 3/4.6.2 DEPRESSURIZATION SYSTEMS......................... B 3/4 6-3 3/4.6.3 PRIMARY CONTAINMENT ISOLATION VALVES............. B 3/4 6-6 3/4.6.4 VACUUM RELIEF.................................... B 3/4 6-6 l

i 3/4.6.5 SECONDARY CONTAINMENT............................ B 3/4 6-6 3/4.6.6 PRIMARY CONTAINMENT ATMOSPHERE CONTROL........... B 3/4 6-7 FERMI - UNIT 2 xiv Amendment No. 49

INDEX I

LIST OF TABLES (Continued) i TABLE PAGE l

4.3.4-1 ATWS RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS......

3/4 3-35 3.3.5-1 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION................................

3/4 3-37 3.3.5-2 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION I

INSTRUMENTATION SETPOINTS......................

3/4 3-39 4.3.5.1-1 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS......

3/4 3-40 3.3.6-1 CONTROL ROD BLOCK INSTRUMENTATION..............

3/4 3-42 t

3.3.6-2 CONTROL R0D BLOCK INSTRUMENTATION SETPOINTS....

3/4 3-44 4.3.6-1 CONTROL ROD BLOCK INSTRUMENTATION SURVEILLANCE REQUIREMENTS...................................

3/4 3-45 3.3.7.1-1 RADIATION MONITORING INSTRUMENTATION...........

3/4 3-48 4.3.7.1-1 RADIATION MONITORING INSTRUMENTATION i

SURVEILLANCE REQUIREMENTS......................

3/4 3-50 3.3.7.2-1 SEISMIC MONITORING INSTRUMENTATION...........,,, 3/4 3-52 4.3.7.2-1 SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS......................

3/4 3-53 3.3.7.3-1 METEOROLOGICAL MONITORING INSTRUMENTATION......

3/4 3-55 I

4.3.7.3-1 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REOUIREMENTS......................

3/4 3-56 3.3.7.4-1 REMOTE SHUTDOWN SYSTEM INSTRUMENTATION.........

3/4 3-58 4.3.7.4-1 REMOTE SHU100WN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS......................

3/4 3-59 3.3.7.5-1 ACCIDENT MONITORING INSTRUMENTATION............

3/4 3-61 4.3.7.5-1 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS......................

3/4 3-63 t

l FERMI - UNIT 2 xxiii Amendment No. 49

l, INDEX l

LIST OF TABLES (Continued) l TABLE PAGE i

3.3.7.9-1 FIRE DETECTION INSTRUMENTATION.................

3/4 3-68 3.3.7.11-1 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION................................

3/4 3-72 4.3.7.11-1 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS......

3/4 3-74 3.3.7.12-1 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION................................

3/4 3-77 4.3.7.12-1 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUtiENTATION SURVEILLANCE REQUIREMENTS......

3/4 3-81 3.3.9-1 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION................................

3/4 3-87 3.3.9-2 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION SETPOINTS......................

3/4 3-88

4. 3. 9.1-1 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS......3/4 3-89 3.4.3.2-1 REACTOR COOLANT SYSTEM PRESSURE ISO VALVES............................LATION 3/4 4-12 3.4.3.2-2 REACTOR COOLANT SYSTEM INTERFACE VALVES LEAKAGE j

PRESSURE MONITORS..............................

3/4 4-12 i

3.4.4-1 REACTOR COOLANT SYSTEM CHEMISTRY LIMITS........

3/4 4-15 l

4.4.5-1 PRIMARY COOLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM...............................

3/4 4-18 4.4.6.1.3-1 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM--

WITHDRAWAL SCHEDULE............................

3/4 4-22 4.6.1.1-1 PRIMARY CONTAINMENT ISOLATION VALVES / FLANGES LOCATED IN LOCKED HIGH RADIATION AREAS.........

3/4 6-lb-3.6.3-1 PRIMARY CONTAINMENT ISOLATION VALVES...........

3/4 6-22 3.6.5.2-1 SECONDARY CONTAINMENT VENTILATION SYSTEM t

AUTOMATIC ISOLATION DAMPERS....................

3/4 6-53 3.7.3-1 SURVEY POINTS FOR SHORE BARRIER................

3/4 7-12 3.7.7.5-1 FIRE HOSE STATIONS.............................

3/4 7-32 3.7.7.6-1 YARD FIRE HYDRANTS AND ASSOCIATED HYDRANT HOSE HOUSES.........................................

3/4 7-37

4. 8.1.1. 2-1 DIESEL GENERATOR TEST SCHEDULE.................

3/4 8-8 FERMI - UNIT 2 xxiv Amendment No.

49

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CONTAINMENT SYSTEMS 3/4.6 CONTAll1 MENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT PRIMARY LCNTAINMENT INTEGRITY LIMITING CONDITION FOR 0PERATION 3.6.1.1 PRIMARY CONTAINMENT INTEGRITY shall be maintained.

APPLICABILITY: GPERATIONAL CONDITIONS 1, 2* and 3.

ACTION:

4 Without PRIMARY CONTAINMENT INTEGRITY, restore PRIMARY CONTAINMENT INTEGRITY within I hour or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

, SURVEILLANCE REOUIREMENTS 4.6.1.1 PRIMARY CONTAINMENT INTEGRITY shall be demonstrated:

Af ter each closing of each penetration subject to Type B testing, a.

except the primary containment air 1cci:s, if opened following Type A or B test, by leak rate testing the seals with gas at P, 56.5 psig, a

and verifying that when the measured leakage rate for these seals is added to the leakage rates determined pursuant to Surveillance Requirement 4.6.1.2.b for all other Type B and C penetrations, the combined leakage rate is less than or equal to 0.60 L,.

b.

At least once per 31 days by verifying that all primary containment penetrations except those inside the containment or in locked high radiationareas(listedinTable4.6.1.1-1)notcapableofbeing closed by OPERABLE containment automatic isolation valves and required to be' closed during accident conditions are closed by locked closed valves, blank flanges, or deactivated automatic valves secured in position, except as provided in Table 3.6.3-1 of Specification 3.6.3.

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1.

Valves, flanges, and deactivated automatic valves which are located inside the containment, and are locked, sealed or otherwise secured in the closed position shall be verified closed during each COLD SHUTDOWN except such verification need not be performed when the primary containnent has not been deinerted since the last verification or more often than once per 92 days.

  • See Special Test Exception 3.10.1.

FERMI - UNIT 2 3/4 6-1 Amendment No.4

CONTAINAENT SYSTEMS PRIMl;g;'ONTAINMENT LEAKAGE SURW "'.ANCE REQUIREMENTS (Continued) 2.

Locked closed valves, flanges, and deactivated automatic valves (listed in Table 4.6.1.1-1) which are located outside the containment within locked high radiation areas shall be verified closed during each COLD SHUTDOWN if not performed within the previous 31 days.**

By verifying each primary containment air lock is in compliance with c.

the requirements of Specification 3.6.1.3.

d.

By verifying the suppression chamber is-in compliance with the require-ments of Specification 3.6.2.1.

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. radiation area access controls if the TIP Room remains a locked high radiation area during COLD SHUTDOWN.

FERMI - UNIT 2 3/4 6-la Amendment No.49'

i TABLE 4.6.1.1-1 PRIMARY CONTAINMENT ISOLATION VALVES / FLANGES LOCATED IN LOCKED HIGH RADIATIONS AREAS PLANT IDENTIFICATION /

VALVE NUMBER LOCATION PENETRATION a.

1.

P34-F013 RWCU Valve X-48F 2.

P34-F014 Pit b.

1.

E21-F023A Reactor Bldg.

X-16B 2.

E21-F022A Second Floor c.

1.

G33-F002 RWCU Valve X-43 2.

G33-F003 Pit d.

1.

821-F017 Steam X-8 2.

B21-F018 Tunnel e.

1.

T48-F006A Reactor Bldg.

X-15 2.

T48-F007A Second Floor f.

1.

C41-F026 RWCU Valve X-42 2.

C41-F027 Pit g.

1.

B21-F025A Steam X-7A, B, C & O 2.

B21-F025B Tunnel 3.

B21-F025C 4.

821-F025D 5.

B21-F026A 6.

B21-F026B 7.

B21-F026C 8.

B21-F0260 h.

1.

B21-F102A Steam

'X-7A 2.

B21-F103A Tunnel i.

1.

G33-F122 Steam X-9B 2.

G33-F123 Tunnel j.

1.

E51-F036 Steam X-10 2.

E51-F037 Tunnel k.

1.

E41-F014 Steam X-11 2.

E41-F015 Tunnel 1.

Penetration.X-35A TIP Room X-35A Blank Flange FERMI - UNIT 2 3/4 6-lb Amendment No. 49

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4 CONTAINMENT SYSTEMS PRIMARY CONTAINMENT LEAKAGE-LIMITING CONDITION FOR OPERATION 2

3.6.1.2 Primary containment leakage rates shall be limited to:

I a.

An overall integrated leakage rate of less than or equal to: L,,

0.5 percent by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P,,

56.5 psig.

b.

A combined leakage rate of less than or equal to 0.60 L, for all penetrations and all valves listed in Table 3.6.3-1, except for main steam line isolation valves

  • and valves which are hydrostatically tested per Table 3.6.3-1, subject to Type B and C tests when pressur-ized to P,, 56.5 psig.

when tested at 25.0 psig.

d.

A combined leakage rate of less than or equal to 5 gpm for all con-tainment' isolation valves in hydrostatically tested lines which penetrate the primary containment,.when tested at 1.10 P,, 62.2 psig, Less than or equal to 1 gpm times the number of valves per penetration e.

not to exceed 3 gpm per penetration for any line penetrating contain-ment and hydrostatically tested-at 1.10 P,, 62.2 psig.

APPLICABILITY: When PRIMARY CONTAINMENT INTEGRITY is required per Specification 3.6.1.1.

ACTION:

1 With; The measured overall integrated primary containment leakage rate a.

j exceeding 0.75 L,, or b.

The measured combined leakage rate for all penetrations and all l

valves listed in Table 3.6.3-1, except for main steam line isolation valves

  • and valves which are hydrostatically tested per Table 3.6.3-1, subject to Type B and C tests exceeding 0.60 L,,'or The measured leakage rate exceeding 100 scf per hour for all four c.

main steam lines, or d.

The measured combined leakage rate for all containment isolation valves in hydrostatically tested lines which penetrate the primary contain-ment exceeding 5 gpm, or The leakage rate of any hydrostatically tested line penetrating primary e.

containment exceeding 1 gpm per isolation valve' times the number of containment isolation valves per penetration or greater than 3 gpm per penetration, prior to increasing reactor coolant system temperature above 200 F, restore:

The overall integrated leakage rate (s) to less than or equal to 0.75 a.

L,,

and

FERMI - UNIT 2 3/46-2 Amendment No. 49

t CONTAINi4ENT SYSTEMS SURVEILLANCE REQUIREMENTS i

0 4.6.5.1 SECONDARY CONTAINMENT INTEGRITY shall be demonstrated by:

Verifying at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> that the vacuum within_the secondary a.

containment is greater than or_ equal to 0.125 inch of vacuum water gauge, b.

Verifying at least once per 31 days that:

1.

All secondary containment equipment hatches' and pressure relief i

doors are closed and sealed, and both railroad bay access doors are closed and sealed.

2.

At least one door in each access to the secondary containment is closed.

3.

All secondary containment penetrations except for Steam Tunnel i

Blowout Panels not capable of being closed by OPERABLE secondary containment automatic isolation dampers / valves and required to be closed during accident conditions are closed by valves, blank flanges, or deactivated automatic dampers / valves secured in the closed position, Verifying Steam Tunnel Blowout Panels are closed during each COLD c.

SHUTDOWN if not performed within the previous-31 days.

d.

At least once per 18 months:

1.

Verifying that one standby gas treatment subsystem will draw down the secondary containment to greater than or equal to 0.25 inch of vacuum water gauge in less than or equal to 567 seconds at a flow rate not exceeding 3800 cfm, and 2.

Operating one standby gas treatment subsystem for I hour and main-taining greater than or equal to 0.25 inch _of vacuum water gauge in the secondary containment at a flow rate not exceeding 3000 cfm.

FERMI - UNIT 2 3/4 6-51a Amendment No. M, 49 i

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3/4.6 CONTAlNMENT. SYSTEM BASES 3/4.6.1 PRIMARY-CONTAINMENT 3/4.6.1.1. PRIMARY _-CONTAINMENT. INTEGRITY l

PRIMARY CONTAINMENT INTEGRITY ensures that the release of radioactive mate--

l rials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in-the safety analyses. This restriction.

l in conjunction with the leakage rate limitation, will limit the SITE BOUNDARY radiation doses to within the limits of 10 CFR Part 100 during accident condi-tions.

PRIMARY CONTAINMENT INTEGRITY is demonstrated by leak rate testing and by verifying that all primary containment penetrations not capable of being closed by OPERA 0LE containment automatic isolation valves and required to be closed during accident conditions are closed by locked valves, blank flanges or deactivated automatic valves secured in the closed position. For test, vent and drain connections which are part of the containment boundary, a threaded pipe cap)with acceptable sealant in addition to the containment l

isolationvalve(s provides protection equivalent to a blank flange.

3/4.6.1.2 PRIMARY CONTAINMENT, LEAKAGE The limitations on primary containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the safety analyses at the peak accident pressure of 56.5 psig, P,.

As an added conserva-tism, the measured overall integrated leakage-rate is further limited to less than or equal to 0.75 L, during performance of the periodic tests to account for possible degradation of the containment leakage barriers between leakage tests.

Operating experience with the main steam line isolation valves has indicated that degradation has occasionally occurred in the leak tightness of the valves; therefore the special requirement for testing these valves.

The surveillance testing for measuring leakage rates is consistent with the requirements of Appendix J of 10 CFR Part 50 with the exception of-exemptions granted for main steam isolation valve leak testing and testing the airlocks after each cpening and analyzing the Type A test data.

Appendix J to 10 CFR Part 50, Paragraph III.A.3, requires that all Type A tests be conducted in accordance with the provisions of N45.4-1972, " Leakage-Rate Testing of Containment Structures for Nuclear Reactors." N45.4-1972 l

requires that Type A test data be analyzed using point-to-point or total time analytical techniques. Specification 4.6.1.2a. requires use of the mass plot analytical technique. The mass plot method is considered the better analytical technique, since it yields a confidence interval which is a small fraction of the calculated leak rate; and the interval decreases as more data sets are added to the calculation. The total time and point-to-point techniques may give con-fidence intervals, which are large fractions of the calculated leak rate, and the intervals may increase as more data sets are added.

l FERMI - UNIT 2 B 3/4 6-1 AmendmentNo.S,4s

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3/4.6 CONTAINMENT SYSTEMS I

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BASES The mass plot method is endorsed by ANSI /ANS 56.8-1981 (Containment System Leakage Requirements) which superseded N45.4-1972.

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3/4.6.1.3 PRIMARY CONTAINMENT AIR LOCKS-The limitations on closure and leak rate for the primary containment air locks are required to mcet the restrictions on PRIMARY CONTAINMENT INTEGRITY-and the primary containment leakage rate given in Specifications 3.6.1.1 and r

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FERMI - UNIT 2 8 3/4 6-la Amendment No. 49 l

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