ML20236C418
| ML20236C418 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  (DPR-69-A-118) |
| Issue date: | 03/15/1989 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20236C422 | List: |
| References | |
| NUDOCS 8903220142 | |
| Download: ML20236C418 (7) | |
Text
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UNITED STATES E
o NUCLEAR REGULATORY COMMISSION g
E WASHINGTON, D. C. 20555
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BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NO. 50-318 CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT 2
_ AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.118 License No. DPR-69 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Baltimore Gas and Electric Company (the licensee) dated December 14, 1988 as supplemented February 17,1989, 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 confonnity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (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 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 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.
DPR-69 is hereby amended to read as follows:
i 8903220142 890315 DR ADOCK 0500 8
l (2) Technical Specifications i
The Technical Specifications contained in Appendices i
A and B, as revised through Amendment No.118, 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.-
.i FOR THE NUCLEAR REGULATORY COMMISSION i
1 R ala. Cn 1
Robert A. Capra, Director Pro.iect Directorate I-1 Division of Reactor Projects, I/II J
i Attachment-4 Changes to the Technical
'j Specifications Date of Issuance: March 15, 1989 1
j i
t 1
m 4
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 118 FACILITY OPERATING LICENSE NO. DPR-69 DOCKET N0. 50-318 Revise Appendix A as follows:
Remove Pages_
Insert Pages
]
3/46-3{t)I 3/4 6-3 3/4 6-3 l
3/4 6-4*
3/4 6-4*
i
'
- Overleaf provided for continuity purposes, i
1 Page 3/4 6-3(t) contains a temporary change that is effective from the date of issuance of this amendment until reaching 199.9*F average reactor coolant system (RCS) temperature during initial i
1 RCS heatup following the Unit 2 Cycle-9 refueling outage.
2 Page 3/4 6-3 replaces page 3/4_6-3(t) and becomes effective upon reaching 199.9'F average reactor coolant system (RCS) temperature during initial RCS heatup following the Unit 2 Cycle 9 refueling outage.
'l
v CONTAINMENT SYEM RURVEILL ANCE REQUIREMENT 1 (Cant;aued) b.
If any periodic Type A test fails to meet either.75 Le (259,500 SCCM) or.75 L (33.400 SCCM), the test achedule for subseevent Type A tests t
shall be reviewed and approved by the Commission. If two consecutive Type A Tests fail to meet aither.75 La (259.500 SCCM) or.75 L t (33,a00 SCCM), a Type A test shall be performed at leest every 13 months until two consecutive Type A tests meet either.75 La (259,500 SCCM) or.75 L (33,400 $CCM) at which time the above test schedute i
may be resumed.
The accuracy of each Type A test shall be verified by a supplemental c.
test which:
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 La (36,500 SCCM) or 0.25 Lt (11,100 SCCM).
2.
Has a duration sufficient to establish accurately the change in kak-age between the Type A test and supplemental testi 3.
Requires the quantity of gas injected lato 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 P (25 psig).
i d.*
Type B and C tests shall te conducted with gas at Pa (50 peig) at intervals no greater than 24 months except for tests involving air locks.
Air locks shall be tested and demonstrated OPERABLE per e.
Surveillance Requirement 4.6.1.3.
f.
All test leakage rates shall be calculated unlag observed data converted to absolute values. F.tror analyses shall be perfornned to select a bal-anced lategrated leakage measurement system.
j Containment purge isolation valves shall be demonstrated OPERABLE any 3
time spos entering MODE 5 from power operation modes, saless the last surveillance test has been performed withis the past 6 months or any i
thee after being opened and prior to estering MODE 4 from shutdown i
modes by verifying that when the measured leakage rate is added to the leakage rates determined pursuant to Taehateal Specification 4.6.1.2.d for all other Type 3 or C penetrations, the combined leaksse rate is less l
than or equal to 0.60 Le (207,600 SCCM). The leakage rate for the costalament purge isolation valves shall also be sempered to the previ-ously measured leakage rate to detect easessive valve degradation.
l h.
The coatsiament purge isolation valve seals shall be replaced with new seals at a frequency to ensure no individual seal remalas in service greater than 2 consecutive fuel reload cycles.
j One-time temporary exemption to Appendix "J" of 10 CFR Part 50 l
and amendment of Surveillance Requirement 4.6.1.2.d providing a 28-day schedular extension for each individual Type B and C test.
{
Expires upon reaching 199.9'F average reactor coolant system (RCS) 1 temperature during initial RCS heatup following the Unit 2 Cycle 9 i
refueling outage.
l A
I
- M2 3/4 6-3(c)
Amendment No. M N.118 1
J
i CONTAINMENT $YSTEMS CONTAINMENT AIR LOCKS L!M: TING CONDITION FOR OPERATION
- 3. 6.1. 3 Each containment air lock shall be OPERA 8LE with.
j a.
Both doors closed except when the air lock is being used for normal transit entry and exit through the containment, then at least one I
air lock door shall be closed, and b.
An overall air lock leakage rate of < 0.05 L, (17.300.$CCN). at P,.
l' 50 psig.
APPLICABILITY: MODES 1. 2. 3 and 4 ACTION:
a.
With an air lock inoperable, except es.a result of an inoperable door gasket, restore the air lock to OPERA 8LE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least NOT $7AN08Y 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
$ HUT 00WN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.-
l 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 l
2.
Restore the air lock to 0PERA8LE status within 7 days or be l
in at least NOT 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 l
$HUTD0WN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
l
$ SURVEILLANCE REQUIREMENTS
- 4. 6.1. 3 Each containment air lock shall be demonstrated OPERA 8LE:
a'.* After each opening, except when the airlock 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) ais determined i
by precision flow measurment when the volume between the door seats is pressurized to a constant pressure of 15 psig, i
- Exeption to Appendix "J" of 10 CFR 50.
l CALVERT CLIFFS - UNIT 2 3/4 6-4 Amendment No. 56
CONTAINAlENT SYSTEMS SURVEILLANCE REOUIREhlENTS (Continued) b.
If any periodic Type A test fails to meet either.75 La (259,500 SCCM) or.75 L (33,400 SCCM), the test schedule for ambsequent Type A tests t
shall be reviewed and approved by the Commission. If two consecutive Type A Tests fail to meet either.75 La (259.500 SCCM) or.75 Lt (33,400 SCCM), a Type A test shall be performed at least every is months until two consecutive Type A tests meet either.75 La (259,500 SCCM) or.75 L (33,400 SCCM) at which time the above test schedule i
may be resumed.
The accuracy of each Type A test shall be verified by a supplemental c.
test which:
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 La (36,500 SCCM) or 0.25 L (11,100 SCCM).
i 2.
Has a duration sufficient to establish accurately the change in leak-age between the Type A test and supplemental test.
1 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 psis) or P (25 psis).
t d.
Type B and C tests shall be conducted with gas at Pa (50 psis) at intervals no greater than 24 months except for tests involving air locks.
Air locks shall be tested and demonstrated OPERABLE per e.
Surveillance Requirement 4.6.1.3.
I f.
All test leakage rates shall be calculated using observed data converted
)
to absolute values. Error analyses shall be performed to select a bal-I anced integrated leakage measurement system.
l 3
Containment purge isolation valves shall be demonstrated OPERABLE any time upon estering MODE 5 from power operation modes, unless the last surveillance test has been performed within the past 6 months or any l
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 Specifiention 4.6.1.2.d for all other Type B or C penetrations, the combined leakage rate is less than or equal to 0.60 La (207,600 SCCM). The leakage rate for the containment purge isolation valves shall also be compared to the previ-ously measured leakage rate to detect excessive valve degradation.
h.
The containment purge isolation valve seals shall be replaced with new seels at a frequency to ensure no individual seal remains in service greater than 2 consecutive fuel reload cycles, q
j Ef fective upon reaching 199.9*F average reactor coolant system (RCS) temperature during initial RCS heatup following the Unit 2 Cycle 9 refuelin CALVERT CLIFFS g outage.
Replaces page 3/4 6-3(t).
UNIT 2 3/4 6-3 Amendment No.
N' 118
CONTAINMENT SYSTEMS CONTAINMENT AIR LOCKS LIMITING CONDIT!UN FOR OPERATION 3.6.1.3 fach 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 b.
An overall air lock leakage rate of 3, 0.05 L, (17,300 SCCN). a t P,,
')
50 psig.
APPLICABILITY: MODES 1. 2, 3 and 4.
ACTION:
a.
With an air lock inoperabia, except as a result of an inoperable coor gasket, restore the air lock to 0PERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 SHUT 00WN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, b.
With an air lock inoperable due to an inoperable door gasket:
1.
Maintain the remaining door of the affected air lock closed ano sealed, and 2.
Restore the air lock to OPERABLE Status within 7 days or be in at least HOT STAND 8Y within the ntxt 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 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE RE UlREM[NTS
- 4. 6.1. 3 Each containment air lock shall be demonstrated OPERA 8LE:
3 a'.* After each opening, except when the airlock 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 saal laakage is < 0.0002 L (69.2 SCCM) s's determined i
by precluion flow sensurement when the volume between the door seals is pressurized to a constant pressure of 15 psig,
- Exenption to Appendix "J" of 10 CFR 50.
1 CALVERT CLIFFS - UNIT 2 3/4 6-4 Amendment No. 56
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