ML20092L493
| ML20092L493 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 02/19/1992 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20092L498 | List: |
| References | |
| NUDOCS 9202260297 | |
| Download: ML20092L493 (14) | |
Text
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BALTlHORE GAS AND ELECTRIC COMPANY QQGET NO. 50-317 CALVERT Cliffs NUCLEAR POWER PLANT 1! NIT NO.1 MiU!DMENT TO FAClllTY OPERATING LICENSE Amendment No. 168 License No. DPR-53 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Baltimore Gas and Electric Company (the licensee) dated November 27, 1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission'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 Comission; 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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 cf the Comission'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, and paragraph 2.C.(2) of Facility Operating License No. OPR-53 is hereby amended to read as follows:
9202260297 920219 PDR ADOCK 05000317 P
2 (2)
Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No 168, 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 REGULATORY COMMISSION
- t$Y 0' 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:
February 19. 1992
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BALLIBORL.GA5JLifDELL181LC0dPMu DXt1LUQJ2-lla CALY1BT Clif fS NKLLAR PDMUL PLANT. UNIT NO. 2 NiLEDEUU_JGC 1 L i 1 Y O P t RAT 1.ELLLC[MS[
Amendment No. 147 License No. DPR-69 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application f or amendtr.ent by Baltimora Gas and Electric company (the licensee) dated November 27, 1991, complies with the standards and requirements of the Atomic Energy Act of 1954, a. amended (the Act) and the Commission's rules and regulations set torth in 10 CFR Chapter I; D.
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 requlations; 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 Commiscion'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, and paragraph 2.C.2 of facility Operating License No. DPR-69 is hereby amended to read as follows:
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(2) lechnical Sngdfications The Technical Specifications contained in A3pendices A and B, as revised through Amendment No. 147, are heresy 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 REGULA10RY COMMISSION K dd O' W Robert A. Capra, Director Project Directorate 1-1 01 vision of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the lechnical Specifications Date of Issuance: February 19, 1992 I
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AT1ACHMENT TO LICENSE AMENDMENTS AMENDMENT NO 168 TO FACILITY OPERATING LICENSE NO. DPR-53
. AMENDMENT NO. 147 10 FAtlllTY OPERATING tlCENSE_ f(0. DPR-69 DOCKEi NOS.10-317 ANIL51-Jla Revise Appendix A as follows:
Bemove Paggi JnietLfust 3/4 6-2 3/4 6-2 3/4 6-3 3/4 6-3 3/4 6-3a (DPR-53 only) 3/4 6-3a 3/4 6-4* (DPR-69 only) 3/4 6-4* (DPR-69 only)
D 3/4 6 1 B 3/4 6-1
- A page that did not change, but is an overleaf.
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CONTAINMENT SYSTEMS p
[0NTAINMENTLEAKAGE UMLT.lNLCM01110!UDfLQHfBILON 3.6.1.2 Containment leakage rates shall be limited to:
4 a.
An overall integrated leakage rate of:
346 1.
1L conla(nmen,000SCCM),0.20percentbyweightofthe i
t 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.
1 L, (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 i
25 psig.
A combined leakage rate of s 0.50 Lpenetrationsandvalvessubjectto b.
173,000 pressurized to P '
a APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
With either (a) tho measured overall integrated containment leakage rate exceeding 0.75 L (259.500 SCCM) or 0.75 Lt (46,200 SCCH), as applicable, or (b) with the measured combined leakage rate for all penetrations and valves subject to Types B and C tests exceeding 0.50 L, restore the a
overall integrated containment leakage rate to less-than or equal to 0.75 L or less than or equal to 0.75 L., as apalicable, and the combined a
leakage rate for all penetrations and v&lves su) ject to Type B and C tests to less than or equal to 0.50 prior to increasing the Reactor Coolant System temperature above 200 ERYEILLAELBEQVlamMLS 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, methods and provisions specified in Appendix J of 10 CFR Part 50:
a.
Three Type _A tests (Overall Integrated Containment Leakage Rate) shall be conducted at approximately equal intervals during shutdown at either P e(50 psig) or at P '(25 psig) t during each 10 year service p riod.
CALVERT Cliffs - UNIT 1 3/4 6 2 Amendment No. 75/EE/JJ//JE/,168 l-
(ON161hMINI 5YSILMS LONIMHtiEKLLEA. AGE K
LIM 111NLCONDLUOM10R.0HMQ0N 3.6.1.2 Containment leakage rates shall be limited to:
a.
An overall integrated leakage rate of:
5Lconta(346,000SCCH),0.20percentbyweightofthe 1.
inment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P ' 60 P5I9' 0F a
2.
1Lt (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,
g 25 psig.
A combined leakage rate of s 0.50 L 173,000 SCCH) for all l
b.
penetrationsandvalvessubjecttotyp(eBandCtestswhen pressurized to P,.
6PfLICABill1Y:
H0 DES 1, 2, 3 and 4.
6,(11DN:
With either (a) the measured overall integrated containment leakage rate exceeding 0.75 L 259.500 SCCH), or 0.75 Lt (33,400 SCCH), as applicable,or($)(withthemeasuredcombinedleakagerateforall penetrations and valves subject to Types B and C tests exceeding 0.50 L '
a restore the overall integrated containment leakage rate to less than or equal to 0.75 L or less than or equal to 0.75 L. a; applicable, and the a
t combined leakage rate for all penetrations and valves subject to Type B and C tests to less than or equal to 0.50 L prior to increasing the ReactorCoolantSystemtemperatureabove2000f.
SMYLILLANCERLOMMMEN15 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, methods and provisions specified in Appendix J of 10 CFR Part 50:
a.
Three Type A tests (Overall Integrated Containment Leakage Rate) shall be conducted at approximately equal intervals during shutdown at either Pa (50 psig) or at Pt (25 psig) during each 10 year service period.
CALVERT Cliffs UNIT 2 3/4 6-2 Amendment No. ES/Ep#EUU,147
CMMIMIN1_SISIMS I
SVUf1UMCLIIIQVIRBMIS_(Continwd) b.
If any periodic Type A test f ails to meet either 0.75 L (46,200SCCM),thetestsched01efor (259,500 SCCM) or 0.75 Lt subsequent Type A tests thall be reviewed and approved by the Commission.
If two consecutive Type A Tests fail to meet Atestshall$e(performedatleastevery18monthsuntiltwot (46,200 SCCM l
either 0.75 L 259.500 SCCM) or 0.75 L t
consecutive Type A tests meet either 0.75L. (259,500 SCCM) or O.75 Lt (46.200 SCCM) at which tims the ab5ve test schedule may be resumed.
i c.
The accuracy of each Type A test shall be verified by a supplemer. cal test which:
I 1.
Confirms the accuracy of the Type A test by verifying that the difference between supplemental and Type A test data is within 0.25 L, (86,500 SCCM) or 0.25 Lg (15.400 SCCM).
2.
Has a duration sufficient to establish accurstely the change in leakage between the Type A test ano supplemental test.
3.
Requires the quantity of gas injected into the containment or bled from the containment during the supplemental test to be equivalent to at least 25 percent of the total i
measured leakage rate at P, (50 psig) or Pt (25 psig),
d.
Type B and C tests shall be conducted with gas at Pa (50 psig) at intgrvals of 24 months except for tests involving air l
locks.
e.
Air locks shall be tested and demonstrated OPERABLE per Surveillance Requirement 4.6.1.3.
f.
All test leakage rates shall be calculated using observed data converted to absolute values.
Error analyses shall be performed to select a balanced integrated leakage measurement system.
g.
Containment purge isolation valves shall be demonstrated OPERABLE any time upon entering MODE 5 from power operation modes, unless the last surveillance test has been performed within the past 6 months or any time after being opened and prior to entering MODE 4 from shutdown modes by verifying that when the measured leakage rate is added to the leakage rates determined pursuant to Technical Specification 4.6.1.2.d for ExemptiontTAppendix"J"to10CfR50.
CALVERT Cliffs - UNIT 1 3/4 6 3 Amendment No. JE/J/E/JE2, 168
LORIAIMLRLEY11thS SVHYL I LLANC LHLOV 1B LHENISEnn tJ n ued b.
If any periodic Type A test fails to meet either 0.75 L (259,500 SCCM) or 0.75 L, (33,400 SCCM), the test sched0le for subsequent Type A tetts ihall be reviewed an approved by tie Commission, if two consecutive Type A lests f ail to nicet either 0 75 L (259.500 SCCM) or 0.75 Lt (33,400 SCCM), a l
Type A test s$all be performed at least every 18 months until two consecutive lype A tests meet either 0.15L (259.500 SCCM) or 0.75 L (33,400 SCCM,' at watch tie the above, test schedule may be resumed.
i c,
The accuracy of each lype A test shall be verified by a supplemental test which:
1.
Confirms the accuracy of the Type A test by verifying tFat the difference between supplemental and Type A test data is within 0.25 L, (86,500 SCCM) or 0.25 Lt (11,100 SCCM).
2.
Has a duration sufficient to establish accurately the change in leakage between the Type A test and supplemental test.
3.
Requires the quantity of gas injected into the containment or bled from the containment during the supplemental test to be equivalent to at least 25 percent of the total measured leakage rate at Pa (50 psig) or Pt (25 psig).
d.
Type B and C tests shall be conducted with gas at Pa (50 psig) at intervals of 24 months except for tests involving air locks.*
e.
Air locks shall be tested and damonstrate1 OPCRABLE per Surveillance Requirement 4.6.13.
f.
All test leakage rates shall be calculated using observed data converted to absolute values, Error analyses shall be performed to selected a balanced integrated leakage measurement system.
g.
Containment purge isolation valves shall be demonstrated OPERABLE any time upon entering MODE 5 ftom power operation modes, unless the last surveillance test has been performed within the past 6 months or any time after being opened and prior to entering MODE 4 from shutdown modes by verifying that when the measured leakage rate is added to the leakage rates determined pursuant to Technical Specification 4.6.1.2.d for all other Type B or C penetrations, the combined leakage rate is less than or equal to 0.50 L 173,000 SCCM),
The leakage I
rateforthecontainroentpurgeiso(lationvalvesshallalsobe compared to the previously measured leakage rate to detect excessive valve degradation.
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Exemption to Appendix "J" to 10 CfR 50.
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l CALVERT Cliffs - UNIT 2 3/4 6 3 Amendment No. EE/JJd/JJS,147 I
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[pNTAINMENT SYSilHS EURYllllMCLREQU1B[E21LIContinu edi all other Type B or C penetrations, the combined leakage rate is less than or equal to 0.50 L 173,000 SCCH).
The leakage rateforthecontainmentpurgeiso(lationvalvesshallalsobe l
compared to the pre';iously measured leakage rate to detect excessive valve degradation, b.
The containment purgs isolation valve seals shall be replaced with new seals at a frequency to ensure no individual seal remains in service greater than 2 consecutive fuel reload cycles.
CALVERT Cliffs UNIT 1 3/4 6-3a Amendment No. 7E/JJE/JJJ,168
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CONIAINMEM_1YSTfMi SURKillMCLREQUIRWWISJContinued) h.
The containment _ purge isolation valve seals shall be replaced with new seals at a frequency to ensure no individual seal remains in service greater than 2 consecutive fuel reload cycles.
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t CALVERT CLIFF 5 UNIT 2 3/4 6 3a Amendment No. JJ/JJp/J/E,147-i
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'i rs J-CDMIA]NMENT-SYSTEMS i
CDMIAINtiMJ AIR LOCKS LIMITING CONDITION f0P OPERATION 2
3.6.1.3 Each containment air lock shall be OPERABLE with:
a.
Both doors closed except'when the air lock is being used for normal transit entry-and _ exit through the containment, then at least one air lock door shall be closed, and
'i t.
An overall air lock leakage rate of 5 0.05 La (17,300 SCCM) at j
P, 50 psig.
a
-APPLICARlLlJ1: MODES 1, 2, 3, and 4.
ACTION:
E a.
With aa-air lock inoperable, except as a resultlof an inoperable door gasket, restore the air lock to OPERABLE status i
within 24 hout s or be in at least HOT STAND 8Y 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-hours, b.
With an air lock inoperable-due to an inoperable door gasket:-
1.
Maintain the remaining door of the affected air lock closed and sealed, and 2.
Restore the air lock to OPERABLE status within 7 days 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 followies 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
EURVEILLANCE REOUIREMENTS 4.6.1.3 Each containment air lock shall be demonstrated OPERABLE:
a.* -- After each opening, except when the air lock is being used for multiple-entries. -then at -least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> by verifying that the seal leakage is < 0.0002 L (69.2 SCCM) as determined l
- by precision _ flow measurement when fhe volume between the door seals is pressurized to a constant pressure of 15 psig.
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ExcepttoAppendIx"J"of10CFR50.
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4 CALVERT CLIFFS - UNIT 2 3/4 6-4 Amendment No. 56
-g.
p 3/4.6 CONTAINMENT SYSTEMS BASES 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 -CONTAINMENT INTEGRITY i
In. MODES 1, 2,=3, and 4, prii iry CONTAINMENT INTEGRITY ensures-that the release of radioactive materi.ls from the containment atmosphere will be restricted to those leakage paths and associated -leak rates assumed in the accident analyses. =This restriction,-in conjunction with the leakage rate limitation, will limit the site boundary radiation doses to within the limits of 10 CFR 100 during accident conditions.- In MODES 5 and 6, the probability and consequences of these events are reduced because of the' Reactor Coolant System (RCS) pressure and temperature limitations of-these modes, by preventing operations which could lead to a need for containment isolation,~and by providing containment isolation through penetration closure.-
3/4.6.1.2-CONTAINMENT LEAKAGE The limitations on containment leakage rates ensure that thel total-containment leakage volume will not exceed the value assumed in the accident analyses at the peak ~ accident pressure, P.
As an added a
conservatism,-the measured overall integrated leakage rate is further
-limited to s 0.75 L -or 0 t (as applicable) during performance of theperiodictestsloaccou.75Lnt for possible degradation of.the containment leakage barriers between leak-tests.
.The surveillance testing.for measuring' leakage rates are consistent' with the requirements of Appendix "J" of 10 CFR 50, excest for the serformance of Type B~and C leakage testing, The allowaale -leakage rate las been proportionately reduced, as recommended in Generic Letter 91404, to account for an extended surveillance schedule of 24 months + 25% (per Specification 4.0,2).
This_is an exemption from Appendix J to 10 CFR Part 50.-
- 3/4.6.l.3 CONTAINMENT AIR LOCKS i
The limitations on closure and leak rate for the containment air-locks are required to meet the restrictions on CONTAINMENT. INTEGRITY and containment leak rate, Surveillance testing of the air lock seals provides assurance that the overall air lock leakage will not become excessive due to seal ^ damage during the intervals between air-lock leakage tests.
CALVERT_ CLIFFS - UNIT 1 B 3/4 6-1 Amendment No. JEE,168
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1 3/4.6 CONTAINMENT SYSTEMS BASES J/_L_6.1 PRIMARY _CONTAINMEN_T 3/4.6.1.1 CONTAINVENT INTEGRITY In H00ES 1, 2, 3, and 4, primary CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the accident analyses.
This restriction, in conjunction with the leakage rate limitation, will limit the site boundary radiation doses to within the limits of 10 CFR 100 during accident conditions.
In MODES 5 and 6, the probability and consequences of these events are reduced because of the Reactor Coolant System (RCS) pressure and temperature limitations of these modes, by preventing operations which could lead to a need for containment isolation, and by providing containment isolation through penetration closure.
3/4.6.1.2 CONTAINMENT LEAKg d The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the accident analyses at the peak accident pressure, P.
As an added a
conservatism, the measured overall integrated leakage rate is further limitedto10.75L(oaccountforpossibledetradationofthecontainment or 1 0,75 Lt (as applicable) during performance of the periodic tests leakage barriers between leakage test >.
The surveillance testing for measuring leakage races are consistent with the requirements of Appendix "J" of 10 CFR 50, except for the performance of Type B and C leakage tasting.
The allowable leakage rate has been proportionately reduced, as reconnended in Generic Letter 91-04, to account for an extended surveillance schedule of 24 months + 25% (per Specification 4.0.2).
This is an exemption from Appendix J to 10 CFR Part 50.
1/4.6.1.3 CONTAINMENT AIR LOCKS The limitations on closure and leak rate for the' containment air locks are required to meet the restrictions on CONTAINMENT INTEGRITY and containment leak rate.
Surveillance testing of the air lock seals provides assurance that the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests.
CALVERT CLIFFS - UNIT 2 B 3/4 6-1 Amendment No. JJE,147
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