ML20210G539

Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B for Type B & C Containment Leakage Rate Testing

ML20210G539
Person / Time
Site:	Davis Besse
Issue date:	07/26/1999
From:	CENTERIOR ENERGY
To:
Shared Package
ML20210G518	List: ML20210G515 ML20210G525 ML20210G539
References
NUDOCS 9908030122
Download: ML20210G539 (16)

Text

'

l LAR %-0012 l Page 21 L

[ INDEX ADMINISTRATIVE CONTROLS l SECTION PAGE

! Meeting Frequency. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-9 Quorum..................................................... 6-9 Review..................................................... 6-10 Audits...................................................... 6-11 Au thority. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-12 Reco rd s. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-12 6.5.3 Technical Review and Control. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-12 6.6 REPORTABLE EVENT ACTION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-12a l

6.7 SAFETY LIMIT VIOLATION OR PROTECTIVE LIMIT VIOLATION. . . . 6-13 6.8 PROCEDURES AND PROGRAMS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-13 6.9 REPORTING REOUIREMENTS 6.9.1 Routine Reports. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-14c 6.9.2 Special R.eports . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-18 '

6.10 RECORD RETENTION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-18 6.11 DELETED l 6.12 HIGH RADI ATION AREA . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-20 6.13 ENVIRONMENTAL OUALIFICATION . . . . . . . . . . . . . . . . . . . . . . . . . . 6-21 1

6.14 PROCESS CONTROL PROGRAM (PCP) . . . . . . . . . . . . . . . . . . . . . . . . . 6-22 6.15 OFFSITE DOSE CALCULATION MANUAL (ODCM) . . . . . . . . . . . . . . 6-22 6.16 CONTAINMENT LEAKAGE RATE TESTING PROGRAM . .. . . . . 6-23 DAVIS-BESSE, UNIT 1 XVI Amendment No. 38,135,170,189,231,

~

9908030122 990726 PDR ADOCK 05000346 P PDR

LAR 96-0012 Page 22 DEFINITIONS REPORTABLE EVENT 1.7 A REPORTABLE EVENT 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:

a. All penetrations required to be closed during accident conditions are either:

1. Capable of being closed by the Safety Features Actuation System, or

2. Closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed positions, except those approved to be open under administrative controlst

b. Au-The equipment hatchec arehatch Ls closed and cealed, l

c. Each air lock is in compliance with the requirements of Specification 3.6.1.3,

d. The containment leakage rates are within the limits of Specification 3.6.1.2, specified in the Containment Leakane Rate Testina Procram. and

c. The sealing mechanism associated with each penetration (e.g., welds, bellows or O-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 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. CHANNEL CALIBRATION may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated.

CHANNEL CHECK 1.10 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.

DAVIS-BESSE, UNIT 1 1-2 Amendment No. 93,135,147,194, I

l l

k^T THIS PAGE PROVIDED FORINFOMAIl0N OKY 3/4 LlHITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0UIREMENTS 3/4.0 APPLICABILITY t IMITING CONDITION FOR OPERATION 3.0.1 Limiting Cor.ditions for Operation and ACTION requirements shall be applicabic during the OPERATIONAL N0 DES or other conditions specified for each speci fication.

3.0.2 Adherence to the requirements of the Limiting Condition for Operation and/or associated ACTION within the specified time interval shall constitute compliance with the specification. In the event the Limiting Condition for Operation is restored prior to expiration of the specified time interval, completion of the ACTION statement is not required.

3.0.3 When a Limiting Condition for Operation is not met, except as provided in the associated ACTION requirements, action shall be initiated within I hour to place the unit in a MODE in which the Specification does not apply by placing it, as applicable, in:

1. 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 />,

2. At least HOT SHUT 00WN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and

3. At least COLD SilUT00WN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Where corrective measures are completed that permi.t operation under the ACTION requirements, the ACTION may be taken in accordance with the specified time limits as measured from the time of failure to. meet the Limiting Condition for Operatio'n. Exceptions to these requirements are stated in the individual .

Specifications. l 1

I 3.0.4 Entry into an OPERATIONAL N00E or other specified applicability condition shall not be made unless the conditions of the Limit,ing Condition for Operation are met without reliance on provisions contained in the ACTION statements unless otherwise excepted. This provision shall not prevent passage through OPERATIONAL N00ES as required to comply with ACTION statements.

3.0.5 When a system, subsystem, train, component or device is determined to be inoperable solely because its emergency power source is inoperable, or solely because its normal power source is inoperable, it may be considered OPERABLE for the purpose of satisfying the requirements of its applicable Limiting Condition for Operation, provided: (1) its corresponding normal or emergency power source is OPERABLE; and (2) all of its redundant system (s),

subsystem (s), train (s), component (s) and device (s) are OPERABLE, or likewise satisfy the requirements of this specification. Unless both conditions (1) and (2) are satisfied, within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> action shall be initiated to place the unit in a H00E in which the applicable Limiting Condition for Operation does not apply by placing it as applicable in:

1. 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 />.

2. At 1 cast HOT SHUT 00WN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and

3. At least COLD SilVT00WN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

This Specification is not applicable in MODES S or 6.

3.0.6 Equipment removed from service or declared inoper'able to comply with ACTIONS may be returned to service under administrative control solely to perfom testing required to demonstrate its OPERA 81(ITY or the OPERABILITY of other . equipment. This is an exception to Specification 3.0.2 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY.

DAVIS M SSE. UNIT 1 3/4 0.) Amendment No. 74-43&rM3- 22/6

LAR 96-0012

~4 l IlilS PAGE PROVIDED APPLICABILITY I Un i l {g I Utt

{g g g t E U s ti U La SURVEILLANCE REOUIREMENTS 1

4.0.1 Surveill'nce a Requirements shall be applicable during the OPERATIONAL MODES or other conditions specified for individual Limiting conditions for Operation unless otherwise stated in an individual Surveillance Requirement.

4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with a maxinium allowable extension not to exceed 25 percent of the specified surveillance interval.

4.0.3 Failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by Specification 4.0.2, shall constitute noncompliance with the OPERABILITY requirements for a Limiting Condition for Operation.

The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed.

The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to permit the completion of the surveillance when the allowable (equipment inoperability) outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Surveillance requirements do not have to be performed on inoperable equipment.

4.0.4 Entry into an OPERATIONAL MODE or other specifie'd applicability condition I shall not be made unless the Surveillance Requirement (s) associated with the Limiting Condition for Operation have been performed within the stated surveillance interval or as otherwise specified. -

4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2 and 3 components shall be applicable as follows:

a. Inservice inspection of ASME Code Class I, 2 and 3 components and inservice testing of ASME Code Class 1, 2 and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a.

b. Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:

l DAVIS-BESSE, UNIT I 3/4 0-2 Amendment No. 77,Jf0,145,197 l

K 1

, LAR 96-0012 Page 25 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT CONTAINMENTINTEGRITY 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 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

' SURVEILLANCE REOUIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:

a. At least once per 31 days by verifying that:

1. 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 those valves that may be opened under administrative controls per Specification 3.6.3.1, and j

2. All-Ihe_ equipment '-'^'-- ---hatch is closed ' -- ' d

b. By verifying that each containment air lock is in compliance with the i requirements of Specification 3.6.1.3

c. By performing required visual examinations of the contaimnent vessel and shield building in accordance with the Containment Leakane Rate Testine Procram.10 CFR

'_-50, App:ndin J, Option E,0c mcdified by appreved ex:=ption:, and in accerd .c "di 6: guide!:ne:: centnin:d in Regulate y Guide 1.163, dated September 1995.

• Except valves, blind flanges, and deactivated automatic valves which are located inside the Shield Building (including the annulus and containment) and are locked, sealed, or otherw%e l secured in the closed position. These penetrations shall be verified closed during each COL. '

SHUTDOWN except that verification of these penetrations being closed need not be performed more often than once per 92 days.

DAVIS-BESSE, UNIT 1 3/46-1 Amendment No. 147,194,205, 4-

LAR 96-0012 i Page 26 CONTAINMENT SYSTEMS l

CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be_in_accordance with the Containment Leakue Rate Testine Procram. limited 4et

a. An overall4ctegmted leakege-rate of G ,' ,0.50 percent 4y-weight-of-the containment m c__ .u.. n.~_.._ ,,, n ,ao

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b-A-eembined leakage rate cf C 0.60 L. der-ell-penetrations and valve:: :;ubjec44e'Pfpe j n a <,,_

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c. A combined leakage rete-of-G0eE4er-all-penetrations 4 hat are :;econdary ,

eentamment byp='; ledage pais, when pre:;';urized-to-Pc

d. A :;ing!c penetration !cdage rate cf f 0.15 L.4er-tiwainment purge and-exhaust isehtien valve specia! te:;t.

APPLICABILITY: MODES 1,2,3 and 4.

ACTION:

With containment leakane rate (s) not within limit (s). restore containment leakane rate (s) within limit (s) 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 followinc 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

a. Ylii elier: (a) $c mesured cvem!! = kft integmted containment ledage rate exceedir; 0.75 L., (b) wii ic me=ured ecmbined ledage ate for all penetretions a ...a..._ , a e,,_-,- _.,___a: n. g..,m. .w<,,s,...ith'.'.. .-^ h.

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b. Ylii a4 ingle-eentainment purge-andexhaust-isolation valve penetratien-having leakege rate exeeeding 0.15 Lot,-restore 1e !cdage rate 4eethin4imits in 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> +er be in at le=t HOT STANDB-Y-within4hece*t4 hours-and-in-GOLD, SHUTDOWN i wiiin 1e fc!!cwing 30 hour3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />s-SURVEILLANCE REQUIREMENTS 4.6.1.2J. The containment leakage rates shall be dclennined in_iucordance with_the Containment Leakane Rate Testing Procram.-demonstmted = fc!!cw';:

LAR 96-0012 Page 27 c Perfc- Type A te t: in :::ctdan : ith 10 CFR 50, Appendin J, Option E, a:

ned!!!:d by approved ene:npticas, nd in 2000 dane:"ith the guidelin:: entained in Regulaterj Guide 1 163, dated Septe:nber,1995.

4.6.1.2.2 A special test shall be nerformed to verify that the containment purce and exhaust isolation valves leakane rate is within the limits specified in the Containment Leakane Rate Testina Procram, by pressuri7. inn the nipinn section including one valve inside and one valve outside the containment to a pressere creater than or eaual to 20 psin:

a. Each time the containment nurne and exhaust isolation valves are opened. within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after valve closure. or prior to enterine MODE 4 from MODE 5. whichever is later.

b. Each time the plant has been in any combination of MODES 3. 4. 5 or 6 for more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, if not performed in tt3revious 6 months.

DAVIS-BESSE, UNIT 1 3/4 6-2 Amendment No. 90,146,160,198, 205, 1

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i DAVIS-BESSE, UNIT 1 3/4 6-3 Amendment No. 90,120,160, 194,198,205, I

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i Pace 3/4 6-4 Deleted DAVIS-BESSE, UNIT 1 3/4 6-4 Amendment No. 90,160,205,

LAR 96-0012 Page 30 Tlil8 PAGE PROVIDED FORINFORMil0N ONLY TABLE 3.6-1 DELETED i

DAVIS-BESSE. UNIT 1 3/4 6-5 Amendment fio.160

LAR 96-0012

Page 31 CONTAINMENT SYSTEMS-CONTAINMENT AIR LOCKS LIMITING CONDITION FOR OPERATION 3.6.1.3 Each containment air lock shall be OPERABLE with:

I

a. Both doors closed except when the air lock is being used for entry and exit, then at least one airlock door shall be closed, and

b. An overall air lock leakage rate in accordance with the Containment Leakane Rate Testine Procram 2 f f 0.002 L::t P:,28 p::i;;.

APPLICABILITY: MODES 1,2,3 and 4.

ACTION:

• a. With one air lock door inoperable in one or more containment air locks, or with the containment air lock interlock mechanism inoperable in one or more containment air locks:

1. Verify an OPERABLE door in each affected air lock is closed within one hour, and

2. Lock an OPERABLE door closed in each affected air lock within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and

3. Operation may then continue provided that an OPERABLE door in each affected air lock is maintained closed and is verified to be locked closed at least once per 31 days, and provided that the containment air lock passes each scheduled performance of the overall air lock leakane rate test. SR i.5.1.3b.

4. Otherwise, be in 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 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

• b. With one or more containment air locks inoperable except as a result of an inoperable air lock door or air lock interlock mechanism:

1. Verify at least one door in each affected air lock is closed within one hour, and

2. Restore air lock (s) to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3. Otherwise, be in 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 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

• Entry and exit through the OPERABLE door is permissible if necessary to perform repairs of

. the affected air lock components. After each entry and exit, the OPERABLE door must be  !

closed without delay.

DAVIS-BESSE, UNIT 1 3/46-6 Amendment No. 194,223, 4

1 LAR %-0012

Page 32 CONTAINMENT SYSTEMS 1

CONTAINMENT AIR LOCKS l

l SURVEILLANCE REQUIREMENTS 4.6.1.3 Each containaant air lock shall be demonstrated OPERABLE:

a. By /:-ifyine :>erformine reauired air lock leakane rate testina in accordance with the Containment Leakane Rate Testine Procram.*.eid e: ne detectahle :: ! !:aha;;: " hen the .

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c. At least once per REFUELING INTERVAL by verifying that only one door in each air l lock can be opened at a time.

'One inoperable air lock door does not invalidate the previous successful performance of the overall air lock leakane test.

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DAVIS-BESSE, UNIT 1 3/4 6-6a Amendment No. 194,223,

3/4.6 CONTAINMENT SYSTEMS LAR 96-0012 BASES age 33 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 CONTAINMENTINTEGRITY 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 safety analyses. This restriction, in conjunction with the leakage rate limitation and air lock door requirements, will limit the site boundary radiation doses to within the limits of 10 CFR 100 during accident conditions.

3/4.6.1.2 CONTAINMENT LEAKAGE As described in Administrative Controls Section 6.16. the Containment Leakane Rate Testina Procram is based on Option B of Annendix J of 10 CFR 50. The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the safety analyses at the peak desien basis loss of coolant accident pressure of 38 psig, P,. As an added conservatism, the measured, overall, as-left integrated leakage rate is

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further limited to s; 0.75 L , during performance of the periodic tests to account for possible degradation of the containment leakage barriers between leakage tests.

The special test for the containment purge and exhaust isolation valves is intended to detect gross degradation of seals on the valve seats. The special test is performed in addition to the Appendix J requirements.

USAR 6.2.4 identifies all penetrations that are secondary containment bypass leakage paths.

3/4.6.1.3 CONTAINMENT AIR LOCKS The limitations on closure and leak rate for the containment air locks are required to meet the restrictions enensure CONTAINMENT INTEGRITY and to meet the restrictions on overall 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. Maintainina containment air locks OPERABLE reauires compliance with the leakane rate test reauirements of the Containment Leakane Rate Testina Pronram which is described in Administrative Controls Section 6.16.

One inonerable air lock door does not invalidate the previous successful performance of the overall air lock leakane test. This is considered reasonable since either air lock door is capable of providina a fission product barrier in th; event of a desian basis accident.

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The air lock interlock allows only one air lock door of an air lock to be opened at a time.

This provision ensures that a gross breach of containment does not exist when CONTAINMENT INTEGRITY is required. Closure of a single door in each air lock is sufficient to provide a leak tight barrier following postulated events. Nevertheless, in MODES 1 through 4, both doors are kept closed when the air lock is not being used for entry and exit, i.e., containment entries / exits, air lock maintenance, or air lock testing.

l DAVIS-BESSE, UNIT 1 B 3/4 6-1 Amendment No. 90,146,160,194 198,205,223,

c LAR E0012 Paga34 CONTAINMENT SYSTEMS -

BASES 3/4.6.1.3 CONTAINMENT AIR LOCKS (Continued)

The surveillance reouirement which verifies thalonly one door in each air lock can be I onened at a time is not oart of the Containment Irakaec Rate Testine Program. Therefore. its test freauency is subiect to the nrovisions of Snecification 4.0.2.

3/4.6.1.4 INTERNALPRESSURE The limitations on containment internal pressure ensure that 1) the containment structure is prevented from exceeding its design negative pressure differential with respect to the annulus atmosphem of 0.5 psi and 2) the containment peak pressure does not exceed the design pressure of 40 psig during LOCA conditions.

The maximum peak pressure obtained from a LOCA event is 37 psig. The limit of 1 psig for initial positive containment pressure will limit the total pressure to 38 psig which is less than !

the design pressure and is consistent with the safety analyses.

3/4.6.1.5 AIR TEMPERATURE The limitations on containment average air temperature ensure that the overall ,

containment average air temperature does not exceed the initial temperature condition assumed I in the accident analysis for a LOCA. j 3/4.6.1.6 CONTAINMENTVESSELSTRUCTURALINTEGRITY l Deleted 3/4.6.1.7 CONTAINMENT VENTILATION SYSTEM Maintaining the containment purge supply and exhaust isolation valves closed with control power removed at all times during MODES 1,2,3 and 4 provides assurance that the safety function of containmendsolation is maintained in the event of a LOCA.

The ACTION statement assures that at least one containment purge supply and exhaust isolation valve is closed in each containment penetration and provides reasonable time to permit closure of an open valve.

3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS 3/4.6.2.1 CONTAINMENT SPRAY SYSTEM The OPERABILITY of the containment spray system ensures that containment depressurization and cooling capability will be available in the event of a LOCA. The pressure reduction and resultant lower containment DAVIS-BESSE, UNIT 1 B 3/4 6-2 Amendment No. 135,205,221,

1 LAR 96-0012 Page 35 ADMINISTRATIVE CONTROLS 6.16 CONTAINMENT LEAKAGE RATE TESTING PROGRAM

a. A program shall establish the leakane rate testina of the containment as reauired by 10 CFR 50.54(o) and 10 CFR 50. Appendix J. Option B. as modified by approved exemptions. This pronram shall be in accordance with the cuidelines contained in Reculatory Guide 1.163.

Performance-Based Containment Leak-Test Program." dated September 1995, as modified by the followinn exc_eptions:

_1. A reduced duration Type A test may be performed usine the criteria and Total Time method specified in Bechtel Topical Report BN-TOP-1. Revision 1.

2. The fuel transfer tube blind flances (containment penetrations 23 and 24) will not be clinible for extended test freauencies. Their Type B test freauency will remain at 30 months. However.

As-found testine will not be reguired.

3. Followingair lock door seal replacement, a door seal leakane rate test to demonstrate that the seal leakane rate is s 0.01 la with the volume between the door seals pressurized to 210 psic is an acceptable alternative to E door seal leakane test at P. or an overall air lock leakane test at-

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b. The peak calculated containment internal pressure for the desien basis loss of coolant lent.P ,

is 38 psin. ~

c. The maximum allowable containment leakane rate. La. at P ..shall be 0.50% of containment air weicht per day. - -

d. Leakane rate acceptance criteria are-

1. Containment leakane rate acceptance criterion is < 1.0 L., Durinn the first unit startup following testine in accordance with this pronram. the lelikane rate acceptance criteria are

$_0.75 lo for Type A tests. < 0.60 La for all penetrations and valves subiect to Type B and Type C tests. and s 0.03 L. for all penetrations that are secondary containment bypass leakane pathji;

2. A sincle penetration leakane rate of s 0.15 L for each containment purce penetration;

3. Air lock acceptance criteria are:

a) Overall air lock leaktue rate is s 0.015 L. when tested at 2 P.,

b) For each door. seal leakane rate is s 0.01 L when the volume between the door seals is

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pressurized to 210 psin.

e. The_ provisions of Specification 4.0.2 do not appiyl to the test frecuencies specified in the Containment 12akane Rate Testina Pronram.

f. The provisions of Specification 4.0.3 are applicable to the Containment Leakane Rate Testinn Pronram.

DAVIS-BESSE. UNIT 1 6-23 Amendment No.

r 1 l

Docket Number 50-346 License Number NPF-3

< Serial Number 2572 Enclosure 2 COMMITMENT LIST THE FOLLOWING LIST IDENTIFIES THOSE ACTIONS COMMITTED TO BY DAVIS-BESSE NUCLEAR POWER STATION IN THIS DOCUMENT. ANY OTHER ACTIONS DISCUSSED IN THE SUBMITTAL REPRESENT INTENDED OR PLANNED ACTIONS BY DAVIS-BESSE. THEY ARE DESCRIBED ONLY AS f

INFORMATION AND ARE NOT REGULATORY COMMITMENTS. PLEASE NOTIFY THE MANAGER - REGULATORY AFFAIRS (419-321-8466) AT DAVIS-BESSE OF ANY QUESTIONS REGARDING THIS DOCUMENT OR ANY ASSOCIATED REGULATORY COMMITMENTS.

COMMITMENTS DUE DATE

1. The Containment Leakage Rate Testing 1. Prior to implementation of Program, as required by Appendix J, Option the amendment B,Section V.B.4, and as referenced in Section (following NRC approval 6.16 of the proposed Technical Specifications, and issuance of the I will be effective prior to implementation of amendment).

the amendment.

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