ML20134K726

Amends 219 & 196 to Licenses DPR-53 & DPR-69,changing TSs in Response to & Adopting Option B,10CFR50,app J to Require Type B & C Containment Leakage Testing to Be Performed on Performance Based Testing Schedule

ML20134K726
Person / Time
Site:	Calvert Cliffs
Issue date:	02/11/1997
From:	Bajwa S NRC (Affiliation Not Assigned)
To:
Shared Package
ML20134K728	List: ML20134K726 ML20134K734
References
NUDOCS 9702140203
Download: ML20134K726 (23)

Text

.

pasog%

e g

y o

UNITED STATES 4

NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2066!M001

....+

e BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NO. 50-317 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NO. I AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.219 License No. DPR-53

1. The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Baltimore Gas and Electric Company (the licensee) dated November 26, 1996, 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 Commission; i

C.

There is reasonable assurance (1) that the activities authorized t

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; I

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; 4

and i

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, and paragrsph 2.C.2. of Facility Operating License No.

DPR-53 is hereby amended to read as follows:

9702140203 970211 PDR ADOCK 05000317 P

PDR

. 2.

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.219, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

1

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 S. Singh Bajwn, Acting Director Project Directorate I-l Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuante:

Februcry 11, 1997 e

}p%q x

8,.-

3 UNITED STATES U

t!

NUCLEAR REGULATORY COMMISSION k.....,/

wAssiwotos, o.c. sosswooi BALTIMCRE GAS AND ELECTRIC COMPANY LOCKET NO. 50 '11R CALVERT CLIFFS NUCLEAR POWER PLANT. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.196 License No. DPR-69

1. The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Baltimore Gas and Electric Company (the licensee) dated November 26, 1996, complies with the l

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 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 i l 2.

Technical Specifications The Technical Specifications contained in Appendices A and B, as i

revised through Amendment No.196, are hereby incorporated in the license. The licensee shall operate the facility in accordance 4

with the Technical Specifications.

i 3.

This license amendment is effective as of the date of its issuance and shall be implemented within 30 days.

l FOR THE NOCLEAR REGULATORY CO M ISSION I

S. Singh Bajwa, Acting Director Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date cf Issuance: February 11, 1997 1

e e

e f

1

I 1

ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 219 FACILITY OPERATING LICENSE NO. DPR-53 AMENDMENT NO. 196 FACILITY OPERATING LICENSE NO. DPR-69 4.

DOCKET NOS. 50-317 AND 50-318 Revise Appendix A as follows:

DPR-53 Remove Paaes Insert Paaes 3/4 6-1 3/4 6-1 3/4 6-2 3/4 6-2 3/4 6-3 3/4 6-3 3/4 6-4 3/4 6-4 3

3/4 6-5 3/4 6-5 1

3/4 9-10 3/4 9-10 t

6-8 6-8 6-9 6-9*

B3/4 6-1 B3/4 6-1 i

DPR-69 Remove Paaes Insert Paaes j

3/4 6-1 3/4 6-1 3/4 6-2 3/4 6-2 3/4 6-3 3/4 6-3 4

3/4 6-4 3/4 6-4 3/4 6-5 3/4 6-5 3/4 9-10 3/4 9-10 6-8 6-8 6-9 6-9*

B3/4 6-1 83/4 6-1 I

i

• Pages that did not change, but are overleaf.

l l-3/4.6 CONTAllOIEN 5YSTDi$

j 3/4.6.1 PRIMRY CONTAIMENT I

CONTAIlflENT INTEGRITY l

LDlITING COMITIO11 FOR OPERATI0li 3.6.1.1 Primary CONTAIMENT INTEGRITY shall be maintained.* 8 APPLICABILITY: 110 DES 1, 2, 3 and 4.

Without primary CONTAIlplENT INTEGRITY, restore CONTAIlplDIT ITY within one hour or be in at least 110T 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 SNUTDOWil within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS 4.6.1.1 Primary CONTAIIMEllT IllTEGRITY shall be demonstrated:

a.

At least once per 31 days by verifying that all penetrations" not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except for valves that are open under administrative control as permitted by 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 110DE 4 following a shutdown where the equipment hatch was opened, by conducting a Type B test in accordance with the Containment Leakage Rate Testing Program.

Hydrogen purge containment vent isolation valves shall be o ned for containment pressure control, airborne radioactivity contro and surveillance testing purposes only.

I The shutdown cooling isolation valves may be opened when the RCS temperature is below 300'F to establish shutdown cooling flow.

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 SNUTD0lNI except that such verification need not be performed more often then once per 92 days.

1 CALVERT CLIFFS - UllIT 1 3/4 6-1 Amendment No. 219

I 3/4.6 CONTAllBIENT SYSTDt$

3/4.6.1 PRIMARY CONTAI MENT Containment Leakaae LIMITIM CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:

l a.

A maximum allowable containment leakage rate, L, as specified in Specification 6.5.6,"ContainmentLeakageRatetestingProgram."

b.

A combined leakage rate of 5 0.60 L, for all penetrations and valves subject to Types B and C tests, as specified in Specification 6.5.6, " Containment Leakage Rate Testing Program.".

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION: With either (a) the measured overall integrated containment leakage rate exceeding the acceptance criteria specified in the Containment Leakage Rate Testing Program, or (b) with the measured combined leakage rate for all penetrations and valves subject to Types B and C tests exceeding 0.60 L, leakage rate for all penetrations and valves subject toresto and the combined Types B and C tests to within the acceptance criteria specified in the Containment Leakage Rate Testing Program, prior to increasing the Reactor l

Coolant System temperature above 200"F.

SURVEILLANCE REQUIREMENTS 4.6.1.2 The containment leakage rates shall be detemined in conformance i

with the criteria, methods, schedule, and provisions specified in the Containment Leakage Rate Testing Program:

l a.

Perfom required visual examinations and leakage rate testing, except for containment air lock testing, in accordance with the 4

Containment Leakage Rate Testing Program, i

t 4

CALVERT CLIFFS - UNIT 1 3/4 6-2 Amendment No. 219

3/4.6 C0ffTAllpIENT SYSTDes 50RVEILLAllCE REQUIREMENTS (Continued)

I b.

Containment purge isolation valves shall be demonstrated 0PERABLE l

any time upon entering MODE 5 from power operation modes, unless the last surveillance test has been perfonned within the past six months or any time after being opened and prior to entering M00E 4 from shutdown modes by verifying that wien the measured leakage rate is added to the leakage rates detennined pursuant to Technical Specification 4.6.1.2.a for all other Type B or C l

penetrations, the combined leakage rate is less than or equal to 0.60 L,.

The leakage rate for the containment purge isolation l

valves shall also be compared to the previously measured leakage rate to detect excessive valve degradation.

c.

The containment purge isolation valve seals shall be replaced I

with new seals at a frequency to ensure no individual seal remains in service greater than 2 consecutive fuel reload cycles.

I CALVERT CLIFFS - UNIT 1 3/4 6-3 Amendment No. 219

l l

i l

3/4.6 CONTAllp4Dfi SYSTDtS 3/4.6.1 PRIMARY LJNTAI MENT Containment Air Locks LIMITING CONDITION FOR OPERATION 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 i

nomal 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 5 0.05 L., as specified in Specification 6.5.6, " Containment Leakage Rate Testing Program".

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

a.

With an air lock inoperable, except as a result of an inoperable door gasket, restore the air lock to OPERABLE 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 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 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 lack closed and sealed, and 2.

Restore the air lock to OPERABLE status within 7 days or be in at least NOT 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 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS 4.6.1.3 Each containment air lock shall be demonstrated OPERABLE:

a.

By perfoming containment air lock leakage rate testing in accordance with the Containment Leakage Rate Testing Program, and I

CALVERT CLIFFS - UNIT 1 3/4 6-4 Amendment No. 219

i 3/4.6 CONTAllfENT SYSTDtS

$URVEILLANCE REQUIREMENTS (Continued)

I b.

At least once per 6 months by verifying that only one door in l

each air lock can be opened at a time.

4 i

}

1 i

l i

CALVERT CLIFFS - UNIT 1 3/4 6-5 Amendment No. 219

a 3/4.9 REFUELIM OPERATIMS 3/4.9.8 SHUTDOWN COOLING ANQ COOLANT CIRCULATION LIMITIM CONDITION FOR OPERATIM 3.9.8.1 At least one shutdown cooling loop shall be in operation.'

APPLICABILITY: MODE 6 at all reactor water levels.

gHQN:

a.

With less than one shutdown cooling loop in operation *, suspend all operations involving an increase in the reactor decay heat load or a reduction in boron concentration of the Reactor Coolant System and, specifically, the charging pum>s sha'I be de-energized and the charging flow paths s tall be closed. Close all containment penetrations providing direct access from one containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

The shutdown cooling pumps may be de-energized during the time intervals required for local leak rate testing of containment penetration numbar 41 pursuant to the requirements of Specification 4.6.1.2.a and/or to permit maintenance on valves l

located in the cosmon shutdown cooling suction line, provided (1) no operations are Demitted which could cause dilution of the i

R+ actor Coo' ant Sym:em boron concentration and, specifically, the ciarging pumps sha be de-energized and the charging flow paths shall be closed, (2) all CORE ALTERATIONS are suspended (3) all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere are maintained closed, and (4) the water level above the top of the irradiated fuel is greater than 23 feet.

b.

The provisions of Specification 3.0.3 are not applicable.

l SURVEILLANCE REQUIREMENTS 4.9.8.1 A shutdown cooling loop shall be detemined to be in operation and circulating reactor coolant at a flow rate of a 1500 gpm at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

a l

The shutdown cooling loop may be removed from operation for up to I hour per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period during the perfonnance of CORE ALTERATIMS in the vicinity of the reactor pressure vessel hot legs.

CALVERT CLIFFS - UNIT 1 3/4 9-10 Amendment No. 219 r

--v

r.

.-m.__._.m

..m..

-____,_m_

m.

.m m...

m_~

.. _... _. ~ _. _.,... ~,, _., _ _ _ _ _ _. _,

f 1

l 6.0 ADMINISTRATIVE CONTROL 5 f

i k.

Limitations on the annual and quarterly doses to a MEMER OF TNE i

PUBLIC from Iodine-131, and all radionuclides in particulate form i

i with half-lives greater than 8 days, in gaseous effluents l

released to areas beyond the SITE BOUNDARY, to be limited:

1.

During any calendar quarter: Less than or equal to 15 mrems to any organ; 2.

During any calendar year: Less than or equal to 30 mrems to any organ; and 3.

Less than 0.1% of the limits of 6.5.5.k(1) and (2) as a result of burning contaminated oil; and 1.

Limitations on the annual dose or dose connitment to any MEMBER OF THE PUBLIC due to releases of radioactivity, and to radiation from uranium fuel cycle sources to be limited to less than or equal to 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

6.5.6 Containment Leakaae Rate Testina Proaram A program shall be established to implement the leakage testing of the containment as required by 10 CFR 50.54(o) and 10 CFR Part 50, Appendix J.

Option B.

This program shall be in accordance with the guidelines l

contained in Regulatory Guide 1.163, "Perfonnance-Based Containment Leak-Test Program," dated September 1995, including errata.

l The peak calculated containment internal pressure for the design basis loss-of-coolant accident, P., is 49.4 psig. The containment design pressure is 50 psig.

The maximum allowable containment leakage rate, L., shall be 0.20 percent of containment air weight per day at P..

Leakage rate acceptance criteria are:

a.

Containment leakage rate acceptance criterion is 51.0 L,.

During the first unit startup, following testing in accordance with this program, the leakage rate acceptance criteria are 5 0.60 L, for Types B and C tests and 5 0.75 L, for Type A tests.

b.

Air lock testing acceptance criteria are:

1.

Overall air lock leakage rate is 5 0.05 L, when tested at t P,.

2.

For each door, leakage rate is 5 0.0002 L, when pressurized to 1 15 psig.

The provisions of Specification 4.0.2 do not apply to the test frequencies specified in the Containment Leakage Rate Testing Program.

CALVERT CLIFFS - UNIT 1 6-8 Amendment No. 219

t 6.0 ADMINISTRATIVE CONTROLS The provisions of Specification 4.0.3 are applicable to the Containment i

i Leakage Rate Testing Program.

6.6 REPORTING REQUIREMENTS The following reports shall be submitted in accordance with 10 CFR 50.4.

6.6.1 Occupational Radiation Exposure Report

• A tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures > 100 mrem /yr l

and their associated man rem exposure according to work and job functions (e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance [ describe maintenance], waste processing, and refueling). This tabulation supplements the requirements of 10 CFR 20.2206. The dose assignment to various duty functions may be estimates based on pocket dosimeter, electronic personal dosimeter or i

thennolumi,nescent dosimeter. Small exposures totalling < 20% of the individual total dose need not be accounted for.

In the aggregate, at i

least 80% of the total whole body dose received from external sources should be assigned to specific major work functions. The report shall be submitted prior to March 31 of each year.

6.6.2 Annual Radioloaical Environmental 0*eratino Report The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in the ODCM, and in 10 CFR Part 50, Appendix I, Sections IV.B.2. IV.B.3 and IV.C.

The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, as well as sumarized and tabulated results of these analyses and measurements in the fonnat of the table in the Radiological Assessment Branch Technical Position, Revision 1. November 1979. The report shall identify the TLD results that represent collocated dosimeters in relation to the NRC TLD program, and the exposure period associated with each result.

In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible.

A single submittal may be made for Calvert Cliffs. The submittal should combine those sections that are connon to both units.

Occupational dose from the Independent Spent Fuel Storage Installation will be reported separately.

CALVERT CLIFFS - UNIT 1 6-9 Amendment No. 219 l

3/4.6 CONTAllMENT SYSTDi$

BASES 3/4.6.1 PRIMARY CONTC HMENT l

3/4.6.1.1 CONTAIISIENT INTEGRITY l

In MODES 1, 2, 3, and 4, primary CONTAllplENT 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 j

accident analyses. This restriction, in conjunction with the leakage rate limitation, will limit the $ITE 50UllDARY radiation doses to within the limits of 10 CFR Part 100 during accident conditions.

In IIODES 5 and 6 j

the probability and consequences of these events are reduced because of the ReactorCoolantSystem(RCS)pressureandtemperaturelimitationsofthese modes, by preventing operations which could lead to a need for containment isolation, and by providing containment isolation through penetration f

closure.

3/4.6.1.2 Containment Leakace Maintaining the containment OPERABLE requires apliance with the visual examinations and leakage rate test requirements t,' the Containment Leakage l

Rate Testing Program. The surveillance testing for measuring leakage rates is consistent with the requirements of 10 CFR rart 50, Appendix J, Option B.

As-left leakage, prior to the first startup after perfoming a required leakage test, is required to be 5 0.60 L (207,600 SCCM) for combined Types 8 and C leakage, and 5 0.75 L between required leakage r Type A leakage. At all other times the acceptance criteria is based on an overal) containment leakage limit of

< 1.0 L (346,000 SCCM). At < 1.0 L, the offsite dose consequences are Bounded,by the assumptions of the safety analysis. Surveillance Requirement frequencies are as required by Appendix J.

These periodic testing requirements verify that the containment leakage rate does not exceed the leakage rate assumed in the safety analysis.

3/4.6.1.3 Containment Air Locks The overall air lock leakage rate is required to be 5 0.05 L. (door seals 17,300S at P., and < 0.0002 L, (69.2 SCCM) when the volume between the is pressurGed to 15 psig. The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAllplENT INTEGRITY and containment leak rate. Surveillance testing of the air lock seals provides assurance that the overall air lock leakage will not becomt excessive due to seal damage during the intervals between air lock leakage tests. The frequency of containment air lock leakage rate testing is specified in the Containment Leakage Rate Testing Program.

CALVERT CLIFFS - UNIT 1 B 3/4 6-1 Amendment No. 219

3/4.6 CONTAIWENT SYSTDIS i

3/4.6.1 PRIMARY CONTAINMEN_T CONTAI MENT INTEGRITY l

LIMITING CMDITIM FOR OPERATIM 3.6.1.1 Primary CONTAIMENT INTEGRITY shall be maintained.* '

APPLICABILITY: M00ES 1, 2, 3 and 4.

i ACTION: Without primary CONTAIMENT INTEGRITY, restore CONTAIMENT INTEGRITY within one hour or be in at least NOT STANDBY within the next i

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SNUTDOW within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

4 i

l SURVEILLANCE REQUIREMENTS 4.6.1.1 Primary CONTAIMENT INTEGRITY shall be demonstrated:

a.

At least once per 31 days by verifying that all penetrations **

not capable of being closed by 0PERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except for valves i

that are open under administrative control as pemitted by 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.

3 c.

By verifying that the equipment hatch is closed and sealed, )rior to entering MODE 4 following a shutdown where the equipment latch was opened, by conducting a Type B test in accordance with the Containment Leakage Rate Testing Program.

i 4

I Hydrogen purge containment vent isolation valves shall be opened for containment pressure control, airborne radioactivity control, and 1

surveillance testing purposes only.

The shutdown cooling isolation valves may be opened when the RCS

}

temperature is below 300*F to establish shutdown cooling flow.

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 5NUTDOW except that such 1

verification need not be performed more often then once per 92 days.

CALVERT CLIFFS - UNIT 2 3/4 6-1 Amendment No. 196

3/4.6 CNTADMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT Containment Leakaae

)

LIMITING CMDITIM FOR OPERATIM 3.6.1.2 Containment leakage rates shall be limited to:

a.

A maximum allowable containment leakage rate, L, as specified in Specification 6.5.6, " Containment Leakage Rate testing Program."

b.

A combined leakage rate of 5 0.60 L,, for all penetrations and valves subject to Types B and C tests, as specified in Specification 6.5.6, " Containment Leakage Rate Testing Program."

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION: With either (a) the measured overall integrated containment 3

leakage rate exceeding the acceptance criteria specified in the Containment Leakage Rate Testing Program, 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 overall integrated containment leakage rate, and the combined leakage rate for all penetrations and valves subject to Type B and C tests to within the acceptance criteria specified in the Containment Leakage Rate Testing Program prior to increasing the Reactor i

Coolant System temperature above 200*F.

i SURVEILLANCE REQUIREMENTS i

4.6.1.2 The containment leakage rates shall be detemined in confomance with the criteria, methods, schedule, and provisions specified in the Containment Leakage Rate Testing Program:

a.

Perfom required visual examinations and leakage rate testing, j

except for containment air lock testing, in accordance with the j

Containment Leakage Rate Testing Program.

l 4

i i

CALVERT CLIFFS - UNIT 2 3/4 6-2 Amendment No. 196

0 3/4.6 C0llTAllpElfT SYSTD15 SURVEILLAllCE REQUIREMEllTS (Continued)

I b.

Containment purge isolation valves shall be demonstrated OPERABLE l

any time upon entering M00E 5 from POWER OPERATION MODES, unless the last surveillance test has beer, perfomed within the past 6 months or any time after being opened and prior to entering M00E 4 from shutdown modes by verifying that when the measured leakage rate is added to the leakage rates detemined pursuant to Technical Specification 4.6.1.2.a for all other Type B or C l

penetrations, the combined leakage rate is less than or equal to 0.60 L,.

The leakage rate for the containment purge isolation l

valves shall also be compared to the previously measured leakage rate to detect excessive valve degradation.

c.

The containment purge isolation valve seals shall be replaced l

with new seals at a frequency to ensure no individual seal remains in service greater than 2 consecutive fuel reload cycles.

l i

i i

l CALVERT CLIFFS - UNIT 2 3/4 6-3 Amendment No. 196

3/4.6 CONTAllfqENT SYSTDt3 3/4.6.1 PRIMARY CONTAINMENT Containment Air Locks LIMITING CMDITION FOR OPERATIM 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 norinal 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 5 0.05 L. as specified in Specification 6.5.6, " Containment Leakage Rate Testing Program."

APPLICABILITY: MODES 1, 2, 3, and 4.

ETigi:

T a.

With an air lock inoperable, except as a result of an inoperable door gasket, restore the air lock to OPERABLE 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 STAND 5Y 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 SNUTDOW 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 and sealed, and 2.

Restore the air lock to OPERABLE status within 7 days or be 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

$NUTDOW within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

59RVEILLANCE REQUIREMENTS 4.6.1.3 Each containment air lock shall be demonstrated OPERABLE:

a.

By perfoming containment air lock leakage rate testing in accordance with the Containment Leakage Rate Testing Program, and l

i CALVERT CLIFFS - UNIT 2 3/4 6-4 Amendment No. 196

i i

3/4.6 CONTAllO4ENT SYSTDiS SURVEILUWICE REQUIREMENTS (Continued)

I b.

At least once per 6 months by verifying that only one door in l

each air lock can be opened at a time.

d 4

0 i

i 4

4 i

CALVERT CLIFFS - UNIT 2 3/4 6-5 Amendment No. 196

t 3/4.9 ltEFUELIM OPERATINS 3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION LIMITIM CONDITION FOR OPERATION 3.9.8.1 At least one shutdown cooling loop shall be in operation.*

l l

APPLICABILITY: MODE 6 at all reactor water levels.

ACTION:

a.

With less than one shutdown cooling loop in operation *, suspend all operations involving an increase in the reactor decay heat load or a reduction in boron concentration of the Reactor Coolant System and, specifically, the charging pumps shaL1 be de-energized ar.d the charging flow paths shall be closed.

Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

The shutdown cooling pumps may be de-energized during the time i

intervals required for local leak rate testing of containment penetration number 41 pursuant to the requirements of Specification 4.6.1.2.a and/or to pemit maintenance on valves l

l located in the common shutdown cooling suction line, provided (1) no operations are permitted which could cause dilution of the Reactor Coo' ant Syr em boron concentration and, specifically, the charging pumps sha' be de-energized and the charging flow paths shall be closed. (2) all C0RE ALTERATIONS are suspended (3) all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere are maintained closed, and (4) the water level above the top of the irradiated fuel is greater than 23 feet.

b.

The provisions of Specification 3.0.3 are not applicable.

j SURVEILLANCE REQUIREMENTS

)

4.9.8.1 A shutdown cooling loop shall be detemined to be in operation and circulating reactor coolant at a flow rate of t 1500 gpm at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

The shutdown cooling loo) may be removed from operation for up to I hour per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period curing the perfomance of CORE ALTERATIONS in the vicinity of the reactor pressure vessel hot legs.

CALVERT CLIFFS - UNIT 2 3/4 9-10 Amendment No. 196

6.0 ADMINISTRATIVE CONTROLS k.

Limitations on the annual and quarterly doses to a MEMBER OF THE

)

PUBLIC from Iodine-131, and all radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents released to areas beyond the SITE B0UNDARY, to be limited:

1.

During any calendar quarter: Less tha. er equal to 15 mrems to any organ; 2.

During any calendar year:

Less than or equal to 30 mrems to any organ; and 3.

Less than 0.1% of the limits of 6.5.5.k(1) and (2) as a result of burning contaminated oil; and i

1.

Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity, and to radiation from uranium fuel cycle sources to be limited to less than or equal to 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

6.5.6 Containment Leakaae Rate Testina Procram A program shall be established to implement the leakage testing of the containment as required by 10 CFR 50.54(o) and 10 CFR Part 50, Appendix J, Option B.

This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, " Performance-Based Containment Leak-Test Program," dated September 1995, including errata.

l The peak calculated containment internal pressure for the design basis loss-of-coolant accident, P,, is 49.4 psig. The containment design pressure is 50 psig.

The maximum allowable containment leakage rate, L, shall be 0.20 percent of containment air weight per day at P.

Leakage rate acceptance criteria are:

a.

Containment leakage rate acceptance criterion is 5 1.0 L..

During the first unit startup, following testing in accordance with this program, the leakage rate acceptance criteria are 5 0.60 L, for Types B and C tests and 5 0.75 L, for Type A tests.

b.

Air. lock testing acceptance criteria are:

1.

Overall air lock leakage rate is 5 0.05 L, when tested at tP.

2.

For each door, leakage rate is 5 0.0002 L, when pressurized to 3 15 psig.

The provisions of Specification 4.0.2 do not apply to the test frequencies specified in the Containment Leakage Rate Testing Program.

i CALVERT CLIFFS - UNIT 2 6-8 Amendment No. 196

i l

~

0 6.0 ADMINISTRATIVE CONTROL 5 i

The provisions of Specification 4.0.3 are applicable to the Containment j

Leakage Rate Testing Program.

l 6.6 REPORTING REQUIREMENTS The following reports shall be submitted in accordance with 10 CFR 50.4.

6.6.1 Occupational Radiation Exposure Reoort*

l A tabulation on an annual basis of the number of station, utility, and l

other personnel (including contractors) receiving exposures > 100 mrem /yr and their associated man rem exposure according to work and job functions (e.g., reactor operations and surveillance, inservice inspection, routine maintenance,specialmaintenance[describemaintenance],wasteprocessing, t

and refueling). This tabulation supplements the requirements of 10 CFR 20.2206. The dose assignment to various duty functions may be estimates i

based on pocket dosimeter, electronic personal dosimeter or themoluminescent dosimeter. Small exposures totalling < 20% of the l

individual total dose need not be accounted for.

In the aggregate, at i

least 80% of the total whole body dose received from external sources 1

should be assigned to specific major work functions. The report shall be i

submitted prior to March 31 of each year.

6.6.2 Annual Radioloaical Environmental Doeratina Report t

i The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted 4

i by May 15 of each year. The report shall include sumaries, i

interpretations, and analyses of trends of the results of the Radiological i

Environmental Monitoring Program for the reporting period.

The material l

provided shall be consistent with the objectives outlined in the ODCM, and j

in 10 CFR Part 50, Appendix I, Sections IV.B.2. IV.B.3 and IV.C.

)

The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to j

the locations specified in the table and figures in the ODCM, as well as sunnarized and tabulated results of these analyses and measurements in the fomat of the table in the Radiological Assessment Branch Technical i

Position, Revision 1. November 1979. The report shall identify the TLD i

results that represent collocated dosimeters in relation to the NRC TLD program, and the exposure period associated with each result.

In the event j

that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for i

the missing results. The missing data shall be submitted in a j

supplementary report as soon as possible.

i 3

A single submittal may be made for Calvert Cliffs. The submittal should combine those sections that are comon to both units.

i Occupational dose from the Independent Spent Fuel Storage l

Installation will be reported separately.

j CALVERT CLIFFS - UNIT 2 6-9 Amendment No. 196 l

.i.-*

3/4.6 CONTAIMENT SYSTDIS BASES' 3/4.6.1 PRIMARY CONTAllelENT 3/4.6.1.1 CONTAIl00ENT INTEGRITY In NODES 1, 2, 3, and 4, primary CONTAllplENT 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 80UllBARY radiation doses to within the limits of 10 CFR Part 100 during accident conditions.

In HDDES 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 Leakaae j

Maintaining the containment OPERABLE requires compliance with the visual examinations and leakage rate test requirements of the Containment Leakage i

Rate Testing Program. The surveillance testing for measuring leakage rates is consistent with the requirements of 10 CFR Part 50, Appendix J, j

Option B.

i As-left leakage, prior to the first startup after performing a required i

leakage test, is required to be 5 0.60 L (207,600 SCCM) for combined (254,500 SCCM) for overall containment i

Types B and C leakage, and 5 0.75 L,between required leakage rate tests Type A leakage. At all other times i

the acceptance criteria is based on an overall containment leakage limit of l

< 1.0 L (346,000 SCCM). At < 1.0 L, the offsite dose consequences are Eounded,by the assumptions of the sa,fety analysis. Surveillance j

Requirement frequencies are as required by Appendix J.

1 These periodic testing requirements verify that the containment leakage rate does not exceed the leakage rate assumed in the safety analysis.

j l

3/4.6.1.3 Containment Air Locks i

The overall air lock leakage rate is required to be 5 0.05 L (door seals 17,300 at P,, and 5 0.0002 L. (ig.

69.2 SCCM) when the volume between the is pressurized to 15 ps The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAllflENT IllTEGRITY and containment leak rate. Surveillance testing of i

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. The frequency of containment air lock leakage rate 4

testing is specified in the Containment Leakage Rate Testing Program.

i i

4 CALVERT CLIFFS - UNIT 2 B 3/4 6-1 Amendment No. 196

---