ML20115H534
| ML20115H534 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 10/15/1992 |
| From: | Marsh L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20115H538 | List: |
| References | |
| NUDOCS 9210270208 | |
| Download: ML20115H534 (8) | |
Text
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., UWITED S'TATES NUCLEAR REGULATORY COMMISSION-1 f,,
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DOCKET N0. 50-341 AMENDMENT TO FACILITY OPE uTING LICENSE L
Amendment No.'88 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 November 16, 1989, as supplemented November 14,_
1991, complies with the standards 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; B.
The facility will operate in conformity with the-application', the=
provisions of the-Act, and the rules and regulations of the i
Commission;-
C.
There is reasonable assurancs (1) 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 conductcd 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 ths public; and
- E.
The issuance of this amendment is in~accordance with 10 CFR Fart
~
51 of the Commission's regulations and all applicable. requirements?
have been. satisfied, s
2.
Accordingly, the license is amended by changes to the' Technical-Specifications as indicated in the attachment to this license-amendment -
and paragraph 2.C.(2) of Facility Operating License No.4 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 f.mendment 'No. 88,. and the Environmental Protect ton;P1an contain.a in Appendix B,.are hereby incorporated in the license.
Deco shall operate the P.cility in accordance with the Technical
~
Specifications and the Environmental Protect' ion Plan.
9210270208_921015 PDR.'ADOCK. 05000341 P.
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4 3.
Further, License Condition paragraph 2.C.(7) is deleted frcin facili_ty Operating License No. NPF-43.*
4 This -licen.e amendment is effective as of its date of issuance with full implementation within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION-W Ledyard B. Marsii, Director Project Directorate Ill-1 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation Attachments:
I.
Changes to the Technical Specifications 2.
Page 4 of license Date of Issuance: Oct.ober 15
.992
- Page 4 is attached, for convenience, for the composite license to reflect this change.
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4 Consumers Power Company _ as specified _.n a letter from Deco to the-Director of Regulation, dated August 13, 1971s and the_ letter from Richard W. McLaren, Assistant Attor'.iey General, Antitrust Division,- U. S. Department of Justice, to Bertram H. Schur, Associate General Counsel, Atomic Er.argy Commission, dated August 16, 1971.
(4)
Safetv/ Relief Valve In-Plant Testina (Section 3.8.1. SSER #5)*
Prior to completing the startup test program,. Deco shall perform a-series of in-plant tests of the safety / relief valves (SRVs).
The acceptance criteria for these tests e.re contained in Section 2.13.9, "SRV Load Assessment by In-Plant Tests" of NUREC 9661, "NRC Acceptanc.e Criteria for the Mark I Containment Loni, Term Program." The results of tiiece tests shall be reported to the-NRC staff within six months of completing this test ser_ies.
(5)
Suppression Pool Temperature Measurements (Section 3.8.1. SSER #5)
DECO 'shall accomplish during the first fuel cycle,- all the tasks described in Es letter dated March 6, 1985, regarding the series of SRV tests which will confirm its methodology.for measuring the-suppression pool bulk temperature.
(6)
Environmental Oualification (Section 3.11. SSER #5)
No later than November 30, 1985, Deco shall envirormentally qualify all electrical equipment according to the provisions of 10 CFR 50.49.
(7)
Deleted
~*The parenthetical. notation following the title of many license conditions-denotes the section of the Safety Evaluation Report-(SER) and/or its supplements wherein the license condition is discussed.
Amendment No. 87, 88
-ATTACHMENT TO LICENSE AMENDMENT NO. 88 FACILITY OPERATING LICENSE NO. NPF-43 QQCKET N0. 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 lice 1:1dicating the area of change. The corresponding overlear pages are also provided to maintain document completeness.
REMOVE
.lEifRI XXIV XXIV 3/4 7-9 3/4 7-9 3/4 7-10a 3/4'7-10b l
l l
l
p INDEX LIST OF TABLES (Continued)
TABLE ILAGE 3.3.7.9-1 DELETED..........................................
3/4 3-68 3.3.7.12-1 EXPLOSIVE GAS M0 hit 0 RING INSTRUMENTATION.........
3/1 3-77 4.3.7.12-1 EXPLOSIVE GAS MONITORING INSTRUMENTATION SURVEILLANCE REQUIR7"ENTS........................
3/4 3-81 3.3.9-1 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION..................................
1/4 3-87 3.3.9-2 FEE 0 WATER / MAIN TURBINE TRIP SYSTEM ACTUAi10N INSTRUMENTATION SET P0lNTS........................
3/4 3-88 4.3.9.1-1 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION lilSTRUMENTATION SURVEILLANCE REQUIREMENTS........
3/4 3-89 3.3.11-1 APPENDIX R ALTERNATIVE SHUTDOWN INSTRUMENTATION..
3/4 3-91 4.3.11.1-1 APPENDIX R ALTERNATIVE SHUTDOWN INSTRUMENTATION SURVEILLANCE REQUIREMENTS........
3/4 3-92 3.4.3.2-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION
-VALVES...........................................
3/4 4-12 3.4.3.2-2 REACTOR COOLANT SYSTEM INTERFACE VALVES LEAKAGE PRESSURE M0NITORS...............................
S/4 4-12 3.4.4-1 REACTOR COOLANT SYSTEM CHEMISTRY LIMITS..........
3/4 4-15 4.4.5-1 PRIMARY COOLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PR0 GRAM................................
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 AUTOMATIC ISOLATION DAMPERS......................
3/4 6-53 4.7.2.1-1 CONTROL ROOM EMERGENCY FILTRATION SYSTEM DUCT LEAK TESTING SURVEILLANCE REQUIREMENTS...........
3/4 7-10b 3.7.3-1 SURVEY POINTS FOR SHORE BARRIER..................
3/4 7-12 4.7.5-1 SNUBBER VISUAL INSPECTION INTERVAL...............
3/4 7-20a 3.7.7.5-1 DELETED..........................................
3/4 7-32 3.7.7.6-1 DELETED..........................................
3/4 7-37 4.8.1.1.2-1 DIESEL GENERATOR TEST SCHEDULE...................
3/4 8-8 FERMI UNIT 2 xxiv Amendment No. 39,ES,E7,E.2,Ef, 88
PtANT SYSTEMS SURVEltiANCF RFOUIREMENTS 4.7.2.1 The control room emergency filtration system shall be demonstrated l
OPERABLE:
a.
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the control room air temperature is less than or equal to 95*F.
b.
'At least once per 31 days by:
1.
Initiating fan operation from the control room with each subsystem, establishing flow for at least 15 minutes through the HEPA filters and charcoal adsorbers.
2.
Verifying flow through the llEPA filters and charcoal (dsorbers for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with the associated emergency makeup-inlet air heater OPERABLE.
The subsystem used to establish the 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> of flow through the HEPA filters and charcoal adsorbers shall be staggered such that each subsystem is utilized at least once per 62 days.
c.
At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire, or chemical' releasc in any ventilation zone communicating.with the system by:
1.
Verifying that the systen satisfies the in-place penetration testing acceptance criteria of less than 1.0% and uses the test procedure guidance in Regulatory Positions C.5.a, C.S.c, and C.5.d of Regulatory Guide 1.52, Revision 2, March 1978, while operating the system at a flow rate'of 1800 cfm i.10% through the makeup filter and 3000 cfm i 10% through the recirculation fil ter.
2.
Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C_.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of-Regulatory Guide 1.57, Revision 2, March 1978, for a methyl -iodide penetration of less than 1.0%; and 3.
Verifying a system flow rate of 3000 cfm i 10% during system operation when tested in accordance with ANSI N510-1980.
d.
After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal 'adsorber operation by verifying -
within 31 days after removal that a laboratory analysis of a-representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, j
meets the laboratory testing criteria of Regulatory Position C.6.a-l of Regulatory Guide 1.52, Revision 2, March 1978, for a methyl-iodide penetration of less than 1.0%.
FERMI - UNIT 2 3/4 7-9 Amendment No. pJ, 88
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SURVEllLANCC REQUIREMEH15 (Continued) h.
At least once per 36 months by verifying that the sections of Control Room Emergency filtration System duct listed in Table l
8 1
4.7.2.1-1, when leak tested-in accordance with ASME N510-1989 I
exhibit inleakage less than the acceptance criteria listed in Table 4.7.2.1-1 for the associated pressures.
4.7.2.2 The portions of the Control Room Emergency Filtration System duct listed below, which ar'e accessible during normal operation, shall be visually inspected -at least once per 365 days for cracking, debonding, or other-2 -
abnormal degradation of the applied silicone sealant. Any such cracking, debonding, or other abnormal degradatian shall be reported in accordance with Specification 6.9.2 within 14 days in a Special Report describing tite findings and giving the intended course of action, including evaluation of and justification for continued plant operation, j
a.
Normal intake between damper T4100f042 and the Control Room wall (Penetration V-430) b.
Normal exhaust between damper T4100F044 and the Control Room wall (Penetration V-429) g I-c.
Discharge of recirculation fans T4100C047, 48 between the discharge flanges on filter train T41000016 and the 5th Floor CCHVAC Equipment Room wall (Penetration V-5048) d.
Division !! supply plenum between the Cnntrol Room wall (Penetration V-431) and the 4th Floor Aux. Building ceiling (Penetration V-9014) e.
Emergency intake between the discharge flange on filter-train 141000011 and the inlet flange on filter train T41000016 I
f.
Recirculation duct between the 5th floor CCHVAC. Equipment Room wall (Penetratic: V-504A) and the inlet flange on filter train T41000016 1
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- ests performed in accordance with ANSI N510-1980 prior to the implementation T
8-I of this requirement satisfy this requirement until the next required performance of the test.
FERMI - UNIT 2-3/4 7-10a AmendmentNo.88-l
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TABLE 4.7.2.1-1
-n Tc EE-CONTROL ROOM EMERGENCY FILTRATION SYSTEM DUCT LEAK TESTING SURVEILLANCE. REQUIREMENTS DUCTS
-a
.i 1.
Harmal' intake between damper T4100F042 and the ' Control Room wall (Penetration V-430) 2.
Normal exhaust = between damper T4100F044 and -
the' Control Rcom wall (Penetration V-429)
'3.
Discharge of recirculation fans T4100C047, 48 t
between tha discharge flanges on ' filter train T41000016 and'the 5th Floor CCHVAC Equipment Room i
wall.(Penetration V-504B) 4.
-Division II supply plenum between the Control Room sf tall (Penetration V-431) and the 4th' Floor Aux.
2.
Building ceiling (Penetration V-9014)
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t Leakags Determined at' Maximum Leakage Determined at Mcximum Negative Pressure Expected For
- Negative Pressure Expected For.
Each Specific Duct During Each Specific Duct During Operation-Acceptance Criteria Normal System Operation With a Sinole Damcer Failure-E
. E Cumulative Total for
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all' four ducts (SCFM).
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