ML20076B011
| ML20076B011 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 07/01/1991 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20076B012 | List: |
| References | |
| NUDOCS 9107090189 | |
| Download: ML20076B011 (12) | |
Text
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pa %q'o, J
E ' 3p s ( 't UNITED STATES 1
NUCLEAR REGULATORY COMMISSION
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'o d @d$. ;/
WASHINGTON. D C. 20555 gm BALTit10RE,,G,AS App, Et,EpT,R,1,C,,Cpp,PA!q PP.Cp,tT. pp,_50-317 C ALVE RT,CL,l F F,S, ppgE AR,, POWER,,PL AtlT, pp,lT, p0.,1 AMEtiDMENT TO FACILITY OPERATitlG LICENSE l
Amendment flo.156 License flo. OPR-53 1.
The t;uclear Regulatory Conmission (the Commission) has found that:
A.
The application for ameM ment by Ealtimore Gas and Electric Company (the licensee) dated April 2, 1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Conmission's rules and regulations set forth in 10 CFR Chapter I; 3.
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 f conducted without endangering the health
' (ii) that such activities will be and safety of the pubit conducted in compliance wich the Conmission's regulations; D.
The issuance of this amendn.ent will net be inimical to the como.on defense and security or to the bealth 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 havj feen satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and parLgraph 2.C.(2) of Facility Operating License No. OPR-53 is hereby amended to read as follows:
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9107C'90189 910701 PDR ADOCK 05000317 P
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(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised thrcugh Amendnient tio.156, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as oi te of it'. issuance and shall be impleniented within E % :..
FOR THE NUCLEAR REGULATORY COMMISS10ti
-R u a. (v Robert A. Capra, Director Project Directorate 1-1 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: July 1,1991
f* ** c <
u 2;3 ff
,n UNITED STAYES
-f i NUCLEAR REGULATORY COMMISSION o.,M J.jkf,f WASHINGTON, D C. 20555 s,
+....
D At T I Mp R,E.,,G,A,5, pp,D, [,L[,C,Tpj p,p!',Pppy DOCKET tt0. 50-318 C AL VERT _Cl J F[S, ppC,L[ AR, P,0WE R, P,L,Att,T,, pp),T, p,0,., 2 AMEt4DMEril 10 FACILITY OPERATlflG LICEf4SE Amendment 110. 136 License flo. DPR-69 1.
The f:uclear Regulatory Conmission (the Cornission) has found that:
A.
The application for amendment by Baltimore Gas and Electric Company (the licensee) dated April 2, 1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Conmission's rules and regulations set forth in 10 CFR Chapter I; C.
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 Consission's regulations;.
D.
The issuance of this amendment will not be inimical to the coneon 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.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, end paragraph 2.C.2 of Facility Operating License flo.
DPR-69 is hereby amended to read as follows:
2
(?),T,ec,hni c,a l, Spe,ci f i cat i on s The Technical Specifications contained in Appendices A and P,, as revised through Amendment No.136, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 30 days.
FOR THE NUCLEAR PEGULATORY COMMISSION Rea. (v Robert A. Capra, Director Project Directorate I-1 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: July 1,1991 i
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l AT T A C HM E N T_.T.O..L.I.C.E _tl.S.E..A.t '.E.ti.D.M.E.N.T.S.
A14ENDMENT NO.155,,[ACl,LJTY OPERA,TjNG LICENSE N0._0PR-53 AMENDMENT t10. j35,, f,A,CJ L 1,TY,,0P Ef ATj tlG, L 1C,EtiSE,110., p,P,R,-69 DOCKET N05. 50-317 AND 50-318 Fevise Appendix A as follows:
Remove Page,s insert Pages 1-1* (DRP-53 only) 1-1* (DRP-53 only) 1-2 1-2 3/4 6-1 3/4 6-1 3/4 6-2*
3/4 6-2*
- Pages that did not change, but are overlief
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DELINITIO*iS 1.0 DEFINED TERMS 1.1 The DEFINED TERMS of this section appear in capitalized type and are applicable throughout these Technical Specifications.
THERMAL POWER 1.2 THERMAL POWER shall be the total reactar core heat transfer rate to the reactor coolant.
RATED THERMAL POWER 1.3 RATED THERMAL POWER shall be a total reactor core heat trarsfer rate to the reactor coolant of 2700 MWt.
OPERATIONAL MODE 1.4 An OPERATIONAL MODE shall correspond to any one inclusive combination of core reactivity condition, power level and average reactor coolant temperature specified in Table 1.1.
ACTION 1.5 ACTION shall be that part of a Specification which prescribes remedial measures required under designated conditions.
OPERABLE - OPERABILITY 1.6 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s).
Implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, normal and emergency electrical power sources, cooling or seal water, lubrication cr other required auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function (s) are also capable of performing their related support function (s).
CALVERT CLIFFS - UNIT 1 1-1 Amendment No. M,)AD,156
s e
DEFINITIONS REPORTABLE EVENT 1.7 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.
CONTAINMENT INTEGRITY 1.8 CONTAINMENT INTEGRITY shall exist when:
1.8.1 All penetrations required to be closed during accident ccnditions are either:
a.
Capable of being closed by an OPERABLE containment automatic isolation valve system, or b.
Closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed positions, except as provided in Table 3.6-1 of Specification 3.6.4.1.
1.8.2 All equipment hatches are closed and sealed, 1.8.3 Each airlock is in compliance with the requirements of Specification 3.6.1.3, 1.8.4 The containment leakage rates are within the limits of Specification 3.6.1.2, and 1.8.5 Tha sealing mechanism associated with each penetration (e.g.,
welds, bellows or 0-rings) is OPERABLE.
CHANNEL CAllBRAIIDH 1.9 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. _
The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated.
CALVERT CLIFFS - UNIT 1 1-2 Amendment No. 29/9f,156
e DEFINITIONS REPORTABLE EVENT 1.7 A REPORTABLE EVLHT shall be any of those conditions specified in Section 50.73 of 10 CFR Part 50.
CONTAINMENT INTEGRITY 1.8 CONTAINMENT INTEGRITY shall exist when:
1.8.1 All penetrations required to be closed during accident conditions are either:
a.
Capable of being closed by an OPERABLE containment automatic isolation valve system, or b.
Closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed positions, except as provided in Table 3.6-1 of Specification 3.6.4.;.
1.8.2 All equipment hatches are closed and sealed, 1.8.3 Each airlock is in compliance with the requirements of Specification 3.6.1.3, 1.8.4 The containment leakage rates are within the limits of Specification 3.6.1.2, and 1.8.5 The sealing mechanism associated with each penetration (e.g., welds, bellows, or 0-rings) is OPERABLE.
CHANNEL CALIBRATION 1.9 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors.
The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CAllBRATION may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated.
I CALVERT CLIFFS - UNIT 2 1-2 Amendment No. JfHE,136
'-E 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained, APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTION:
Without primary CONTAINMENT INTEGRITY, restore r.0NTAINMENT INTEGRITY within one hour or be in at least il0T STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SilUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SJ)RVEILLANCE RE0VIREMENTS l -
4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:
At least once per 31 days by verifying that all penetrations
- a.
not capable of being closed by OPERABLE containment automatic
! solation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except as provided in Table 3.6-1 of Specification 3.6.4.1.
b.
By verifying that each containment air lock is in compliance with the requirements of Specification 3.6.1.3.
By verifying that the equipment hatch is closed and sealed, c.
prior to entering MODE 4 following a shutdown where the equipment hatch was opened, by conducting a Type B test per Appendix J to 10 CFR Part 50.
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Except valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked, sealed, or otherwise secured in the closed position.
These penetrations shall be verified closed during each COLD SilUIDOWN except that such verification need not be performed more often than once per 92 days.
CALVERT CLIFFS - UNIT 1 3/4 6-1 Amendment No. S UJJ/,156
i 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT Mt{TAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hot!rs.
SURVEILLANCE RE0VIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:
At least once per 31 days by verifying that all penetrations
- a.
not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed durin conditions are closed by valves, blind flanges, g accident or deactivated automatic valves secured in their positions, except as provided in Table 3.6-1 of Specification 3.6.4.1.
b.
By verifying that each containment air lock is in compliance with the requirements of Specification 3.6.1.3.
c.-
By verifying that the equipment hatch is closed and sealed, prior to entering MODE 4 following a shutdown where the equipment hatch was opened, by conducting a Type B test per Appendix J to 10 CFR Part 50.
Except valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked, sealed, or otherwise secured in the closed position.
These penetrations shall be verified closed during each COLD SHUTDOWN except that such verification need not be performed more often than once per 92 days.
CALVERT CLIFFS - UNIT 2 3/4 6-1 Amendment No. E/EE/99, 136
LONTAINMENT SYSTEMS CONTAINMENT LEAKAGES LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:
a.
An overall integrated leakage rate of:
1.
1La (346,000 SCCM), 0.20 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, 50 psig, or a
-2.
1Lt (61,600 SCCM), 0.058 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 a reduced pressure of P '
t 25 psig.
b.
A combined leakage rate of s 0.60 L penetrations and a.lves subject to iyp(207,600 SCCM), for all e B and C tests when pressurized to P
- a APPLICABILITY: MODES 1, 2, 3, and 4.
A(11011:
With either (a) the measured overall integrated containment le_akage rate exceeding 0.75 La (259,500 SCCM) or 0.75 Lt (46,200 SCCM), as applicable, or (b) with the measured combined leakage rate for all penetrations and valves subject to Types B and C tests exceeding 0.60 L, restore the a
leakage rate (s) to within the limit (s) prior to
- increasing the Reactor Coolant System temperature above 200 F, 0
10RVEILLANCE RE0VIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10_CFR Part 50 using the methods and provisions of ANSI N45.4 - 1972:
a.
Ihree Type A tests (overall Integrated Containment Leakage Rate) shall'be conducted at 40
_10 month intervals during shutdown at either Pa (50 psig) or at Pt (25 psig) during each 10-year service period 1
CALVERT CLIFFS - UNIT 1 3/4 6-2 Amendment No. ##E,112,156
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CONTAINMENT SYSTElil
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[QNTAINMENT LEAKAGES LIMITING CONDITION FOR OPERATION
'3.6.1.2 Containment leakage rates shall be limited to:
a.
An overall integrated leakage rate of:
1.
1L 346,000 SCCH), 0.20 percen*. by weight of the conla(inmentairper24hoursatP,50psig,or a
2.
5Lt (44,600 SCCM), 0.042 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 a reduced pressure of P '
t 25 psig.
l b.
A combined leakage rate of s 0.60 L 207,600 SCCM) for all penetrationsandvalvessubjecttoiyp(e8andCtestswhen l
pressurized to P -
a APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
With either (a) the measured overall integrated containment leakage rate exceeding 0.75L$)(withthemeasuredcombinedleakagerateforall 259,500_SCCM), or 0.75 Lt (33,400 SCCM), as applicable,.or (
penetrations-and valves subject to Types B and C tests exceeding 0.60 L '
a restore the leakage rate (s) to within the limit (s)- )rior to increasing the Reactor Coolant System temperature a)ove 200 F.
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l SURVEILLANCE RE0VIREMENTS l
l 4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the L
criteria specified.in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4 - 1972:
t' a.
Three Type A tests (Overall Integrated Containment Leakage i
Rate) shall'be conducted at 40 10' month intervals during shutdown at either-P -(50 psig)-or at Pt (25-psig) during each 10-yearserviceperi$d.
L.
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CALVERT CLIFFS - UNIT 2 3/4-6-2 Amendment No. # #p,M 136
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