ML20028H025
| ML20028H025 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 09/25/1990 |
| From: | Pierson R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20028H026 | List: |
| References | |
| NUDOCS 9010050193 | |
| Download: ML20028H025 (7) | |
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UNITED STATES.
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- NUCLEAR REGULt. TORY COMMISSION
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DETPOIT EDISON COMPANY DOCKET NO. 50-341 FERMI-2 AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No. 58 License No. NPF-43 i
-1.
The Nuclear Regulatory Conn.ission (the Commission) has foun'd that:
A.
The application for an+ndn<ent by the Detroit Edison Company.(the licensee)datedJuly 24,'1989, cortplies with the standards and requirerrents of the Aten.ic Energy Act of 1954, as arrended (the Act),
and the Constission's rules and regulations set forth in 10 CFR
. Charter I; B.
The' facility will cperate in conformity with the application, the j
provisions cf the Act, and the rules and regulations of the' Cormissicn; C.
Thereisreasonableassurance(i)thattheactivitiesauthorizedby this anendo.ent can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in cortpliar.ce with the Cor.vission's regulatiens; D.
The issuance.of this enendnent will r,ct be inimical to the cone:on
. defense and security or' to the health and safety of the tlic; and-E.
The issuance of this an+ndn;ent.is'ir: accordance with 10 CFR'Part 51 of the Corrission's regulations and all applicable requirements have beer. satisfied.
Accordingly, the,d in the ett:.chmeet to this license amendment andlicense is amended 2.
tions as indicate paragraph'2.C.(?) of 'iacility Operating License No. NPF-43 is hereby
-amended to read as follows:
Technical, Specifications and Environmental Protection Plan s
LThe Technical Specifications contained in Appendix A, as revised through Amendment No. 58, and the Environmental Protection Plan cont:.ined in Appendix B, are hereby. incorporated in the license.
DECO shall operat'e the facility in accordance with the Technical.
Specifications and the Environnental Protection Plan.
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9010050193 90091.5 PDR -ADOCK 05000341 P
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n 2.' Tris.. licerise 6n.eridtent' is effective as of its date of issuance.
FOR Tli h0 CLEAR REGULATORY CDP.P.1SS10N y
- c. l Robert C. Pierscri. Director t.'
Project Directorate 111-1 Division of Rer7 tor Projects - 111, 1
IV, V & Spec.a1 Projects-tifice of Hucitar Reactor Regulation Att6thn. erit :
4 Cherses to tht Techriical Specificaticos Cate of Issott,te: Seotember-25,1990 1
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j ATTACHFEi1TTOLICENSEAMENDMENT-NO.SS.
FAClllTY 0FEFATING LICENSE NO. NPF-43
-l DOCKET 140, 50-341 l
Replace the fc110 wing pages of the Appendix "A" Technical Specifications with the attethed pages. The revised pages are ideritified by Arendnent nunter and
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centain a vertical line itdic6 ting tht-area of change. The corresperding overitof pages are also provided to r6tritain docun+nt completenet.s.
REMOVE INSERT j
3/4 6-13*
3/4 6-13*
3/4 6-14 3/4 6-14 B3/4 6-2 B3/4 6-2 D3/4 6-3 ES/4 6-3 t
i 3DVeileaf page provided to r.aii.tain decupent coriple ttness. 1:e changes contairitd
-in these pages.
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C0tiit 10.E t.1,,5),5,1,IF,S.
DRYWELL-AVERAGE AIR'1EMPERATURE LIMITING CONDITION FOR OPERA 110N 3.6.1.7 Drywell average air temperature shall not exceed 145'F.
A,PP,L,1,CABILITY : OFERATIONAL CONDITIONS 1, 2, and 3.
ACT10h:
With the drywell average air ten:perature greater thor 145'F, reduce the average air temperature to within the liniit within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in at least HOT SFUTDOWN within the rext 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 />.
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-4.6.1.7 The-drywell tverage air terptreture shall te the volunie-tric average p
of the terrperatures at the followirg locations and stell be deterniined to be wittis. the liniit at least once per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s:
L Elevation Azimuth (Atleastoneeteachelevation)
E.
590'0" 90', 135', 270' or 316*
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b.
597'0" 35*, 75*, 93', 135', 175', 200*,.246*,
272', 306' or 345' j
c.
621'8" 0', 90', 180' or 270*
L d.
648'6" 45', 135', 225* or 315' e.
662'0" 0',-90', 180* or 285' f.
665'6" O' or 180' L
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FERit! - UtilT 2 3/4 6-13 An.endment No. PP, 58
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CONTAINM,Epy,,SyS,TJf,5
. DRYWEL L AND,,S,U,Pf,h,E,5,5,lpp,,CpAf,B,Ep,,p0,Rp,E, SJ,5,1 Qt D
LlHIT1kG CCSDITION FOR OPERATION PO-inch, and 24-inch valves)pressict charter purge systein (6-inch,'10-inch, 3.6.1.0 The drywell and sup ray be in operatiori with the supply and exhaust isolaticr. valves in one surply line and one exhaust line open for inerting, deitierting or pressurt control.
Nitrogen VENTING /r.akeup and pressure. control is alsc. allowed through the 1-inch velves.
Purge / vent operations through the 1
SGTS shall be lirnited to 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> each 365 days.*
APPLICABILITY: CFELATIONAL CONDITIONS 1, P ar.d 3.
AL110h:
a.
With a drywell erd suppression. (h6nber purge systtr. surply and/or exheust isol6ticr. valve cpen, e> cept as prtiitted above, close the valve (s) or otherwise isolate the penetraticn(s) withir 4 hcur5 or be in et leest DOT SHUTCCkT vithin the next 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> s and in COLD SHUTCCKf:
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v.ithis, the follesing 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.
With a drywell trd suppressier thenber purge systtr supply and/or extbust isoletict velve(s) with tuilient p.ateriel seals havirc e na-I-
surtd it.e kogt rett t ycu dirig tht. lin.it of: Specificaticn 4.6.1.5.?,
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rotoit tie inoperable velyt(s) to OPERACLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or L
t4 fr at 1ttst F0T SHUTDOWN within the next 12 hocrs and in CCLD SHUTCCWl: within the fc11 chir 9 F4 hours.
S U R V E l l,L,Ap{ { R EQ U I R EM E lri,5,,,,,,,,,,,,,,, _,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,.,.
4.6.1.8.)
Before being opened for purge /verit operatiori through SCTS, the dry-well and suppressici. chanber purge supply arid exhaust butterfly isoletion valves shell be verified r;r.t to bbve Leen open for purge / vent oper6 tion through SGTS for n. ore than 90 heurs in the previous 365 days.*
4.6.1.8.?. At least once per 92 days each penetratier. for each 6-inch, each 10 %ch, each 20-inch, and each 24-inch drywell and suppressicn charber purge supply and exhaust isc16 tion valve with resilient naterial se.als shall be.
l dnoristrated OPERABLE by verifyir.g that the r:easured leakage rate is less than or equal to 0.05 L, when pressurized to P,.
- Prirnary coritairin tr t nitrogen VENTINC sr.c pressor t control 11 prnitted through the 1-irct velves and is not soldett to thE 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> per 365 cay lin.it, j
FERPI-UMl' 3/4 6-14 An'endnent Mc. 58
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C0tlTAl LME,h,1,,S,Y5,Tf BASES -PRIMARYCONTAliFEhT'AIRLOCKS(Continued) L L 3.6.1.2. The specification makes allowances for the fact thet there.may be long periods of titie when the sir locks will be in a closed and secured-B siticn durir.g reactor operation. Only one closed door in each air lock is required to m6intain the integrity of the contaiteent. 3fa.6.1.4 MSIV LEAKAGE CONTROL SYSTEM i Calculated doses resulting froni the n.axirnum leakage allevance for the snair. L steamline isolaticr. valves in the postulated LOCA situations would be a small , fraction of the 10 CFR Part 100 guidelines, provided the main steem lira system from the isolaticn valves up to arid it.cibdirig the turbine ccndenser ren6 ins int 6ct. Operating experience has indicated th6t digt etation has occasionally occurred in the-lett tightness of the MSIVs such that the specified leakagt requirentnts bevt not alwtys teen treint61ried continuously. The requiremer.1 for the leakage control systet will reduce the untreated le6kag~e fron the MSIVs whte isc1611cn cf the prin.ary system t.r.d contaireer.t is required. 1/a.6.1.5 PRil'Afd C0liTAINMENT STRUCTURAL INTEGRITY. This-lineitation ensures th6t the structurel integrity of.the conteinmerit will Lt. nt. int 6ined corproble to the origin 61 de: sign standards for tte life of the unit. StrLctural irittgrity is required to ensure that the cor.taireer.t will withstand the ratyimum pressure of 56.5 pig in the event of a LOCA. A visual inspection ir. ccnjunction with Ty A leakege tests is sufficier.t to l door.strete this c6pbility. 1_ H 3 /4. 6.1. 6.. P.R.Y.W.E.L.L..A.ll.D..S.U.P.P.R.E.S.S.10.t: C.H.A.l.E.E.R..l.ir.I.E.F* A.L..P.R.E.S.S.U.R.E \\ L Ttt lin.it6tions on drywell and suppression chamber internt1 pressure l ensure thbt the cortai0mtr.t peak pressure of 56.5 psig does not exceed the L toaxinum aikwalle pressure of 67 psig during LOCA cor diticos cr that the external p tssure differentiel dcts not exceed the design E6ximurr external l pressure differential of ? psid. 3 / 4. 6.1,.J _ O R Y W E L L,,A,V,E,R,A,G,E,,A,1,R,,T,Ef(P,E,R,A.T,U,R,E The limitation en drywell average air temperature ev.res that the containnent peak air temperature does not exceed the desist temperature of 340'F during LOCA conditions and is consistent with the safety analysis. 3/4.6.1.8 DRYWELL-AllD SUPPRESSION CHAMBER PURGE SYSTEM The drywell and suppression chamber purge supply and exhaust isolation valves are maintained closed during a majority of the plant operating tine. M61r.thining these valves closed (even though they have been qualified to close against the buildup of pressure in prir.iary containtrer.t in the event of DBA/LOCA) rtduces the potentibi for release of excessive qu6ntities of radioactivt; m6terial. 1 j. FERMI - UH1T 2 B 3/4 6-2 Amendment flo. E, 58
g y ? ,2 y q,;} r CONTAINMENT SYSTEMS -BASES DRYWELL AND SUPPRESSION CHAMB'R' PURGE SYSTEM '(Continued) E Purging or venting through the Standby Gas Treatment System (SGTS) imposes a vulnerability factor on the integrity of the SGTS. Should a LOCA occur while the purge pathway is through the SGTS the associated pressure surge, before the purge valves close, may adversely stfect the integrity of 1 the SGTS charcoal filters. Therefore, PURGING or VENTING through the SGTS is limited to 90. hours per 365 days. This time limit is not imposed when venting 'through the SGTS with the 1-inch valves or when PURGING or VENTING through the J Reactor Building Ventilation System with any of the purge valves. Leakage integrity tests with a maximum allowable leakage. rate for purge supply and exhaust isolation valves will provide early indication of resilient (, material seal degradation and will allow the opportunity for repair before gross leakage failure develops. The 0.60 L, leakage limit shall not be L exceeded when the leakage rates deter 91ned-by the. leakage integrity tests of these valves are added to the previously determined total for all valves and penetrations subject,to Type B and C tests. I l The 6, 10, 20, and 24-inch purge valves are generally configured in a three (3) valve' arrangement at each of the associated purge penetrations. The valves .I are leak tested by pressurizing between the three valves and a total leakage f is determined as opposed to a single valve leakage. Verifying that the measured leakage rate is less thn 0.5 L"for a single valve. for this' multi-valve arrangement is more conservative than a limit. 0.5 L, 3/4.6.2 DEPRESSURIZATION SYSTEMS The specifications of this section ensure that the primary containment pressure will-not exceed the maximum allowable pressure of 62 psig durii,;: primary system blowdown from full operating pressure, i The suppression chamber water provides the heat sir.P for the reactor coolant E ' system energy release following a postulated rupture of the system. The suppres-sion chamber water volume must absorb the associated decay and structural sen-sible heat released during reactor coolant system blowdown from 1040 psig. Since all of the gases in the drywell are purged into the suppression chamber air space during a loss-of-coolant accident, the pressure of the liquid must not exceed 62 psig, the suppression chamber maximum pressure. The design volume of the suppression charber, water and air, was obtained by considering. that the total volume of reactor coolant to be condensed is discharged to the suppression chamber and that the drywell volume is purged to the suppression-
- chamber, l
l FERMI - UNIT 2 8 3/4 6-3 Amendment No. 58}}