ML20062E708

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Tech Specs 3.4.3,4.4.3,4.4.10.1.2,6.7,6.8,Table 3.7-4, 3.6.1.2,4.6.1.2,3.6.1.3,4.6.1.3,4.6.4.1.3,4.6.4.1.4 & 4.6.4.1.2 Re RCS Operation & Surveillance Requirements
ML20062E708
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 08/02/1982
From:
BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML20062E704 List:
References
NUDOCS 8208100282
Download: ML20062E708 (15)
v • d • e


Text

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REACTOR COOLANT SYSTEM RELIEF VALVES LIMITING CONDITION FOR OPERATION 3.4.3 Two power operated relief valves (PORVs) and their associated block valves shall be OPERABLE.

APPLICABILITY: MODES 1,2, and 3.

ACTION:

a. With one or more PORV(s) inoperable, within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> either restore the PORV(s) to OPERABLE status or close the associated block valve (s) and remove power from the block valve (s); otherwise, 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 />,
b. With one or more block valve (s) inoperable, within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> either restore the block valve (s) to OPERABLE status or close the block valve (s) and remove power from the block valve (s); otherwise, 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 />.
c. The provisions of Specification 3.0.4 are not applicable. l SURVEILLANCE REQUIREMENTS (Continued) 4.4.3.1 Each PORV shall be demonstrated OPERABLE:
a. Once per 31 days by performance of a CHANNEL FUNCTIONAL TEST, excluding valve operation, and
b. Once per 18 months by performance of a CHANNEL CALIBRATION.

4.4.3.2 Each block shall be demonstrated OPERABLE once per 92 days by operating the valve through one complete cycle of full travel. This demonstration is not required if a PORV block valve is closed and power removed to meet Specification 3.4.3 a or b.

8208100282 820802 PDR ADOCK 05000317 p PDR CALVERT CLIFFS - UNIT 1 3/4 4-4 Amendment No. 53 CALVERT CLIFFS - UNIT 2 Amendment No. 36 L

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)

In addition to the requirements of Specification 4.0.5, each Reactor Coolant Pump flywheel shall be inspected per the recommendations of Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1, August 1975.

4.4.10.1.2 Augmented Inservice Inspection Program for Main Steam and Main Feedwater Piping - The unencapsulated welds greater than 4 inches in nominal diameter in the main steam and main feedwater piping runs located outside the containment and traversing safety related areas or located in compartments adjoining safety-related areas shall be inspected per the following augmented inservice inspection program using the applicable rules, acceptable criteria, and repair procedures of the ASME Boiler and Pressure Vessel Code,Section XI, 1974 Edition and Addenda through Summer 1975, for Class 2 l components,

a. System integrity and baseline data shall be established by performing a 100%

volumetric examination of each weld prior to exceeding 18 months of operation,

b. Each weld shall be examined in accordance with the above ASME Code requirements, except that 100% of the welds shall be examined, cumulatively, during each 10 year inspection interval. The welds to be examined during each inspection period shall be selected to provide a representative sample of the conditions of the welds. If these examinations reveal unacceptable structural defects in one or more welds, an additional 1/3 of the welds shall be examined and the inspection schedule for the repaired welds shall revert back to the first 10 year inspection program. If additional unacceptable defects are detected in the second sampling, the remainder of the welds shall also be inspected.

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CALVERT CLIFFS - UNIT 1 3/4 4-28 Amendment No.

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REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)

In addition to the requirements of Specification 4.0.5, each Reactor Coolant Pump flywheel shall be inspected per the recommendations of Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1, August 1975.

4.4.10.1.2 Augmented Inservice Inspection Program for Main Steam and Main Feedwater Piping - The unencapsulated welds greater than 4 inches in nominal diameter in the main steam and main feedwater piping runs located outside the containment and traversing safety related areas or located in compartments adjoining safety-related areas shall be inspected per the following augmented inservice inspection program using the applicable rules, acceptable criteria, and repair procedures of.the ASME Boiler and Pressure Vessel Code,Section XI, 1974 Edition and Addenda through Summer 1975, for Class 2 l components.

a. System integrity and baseline data shall be established by performing a 100%

volumetric examination of each weld prior to exceeding 18 months of operation.

b. Each weld shall be examined in accordance with the above ASME Code requirements, except that 100% of the welds shall be examined, cumulatively, during each 10 year inspection interval. The welds to be examined during each inspection period shall be selected to provide a representative '; ample of the conditions of the welds. If these examinations reveal unacceptable structural defects in one or more welds, an additional 1/3 of the welds shall be examined and the inspection schedule for the repaired welds shall revert back to the first 10 year inspection program. If additional unacceptable defects are detected in the second sampling, the remainder of the welds shall also be inspected.

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. CALVERT CLIFFS - UNIT 2 3/4 4-29 Amendment No.

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

2. Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following completion of maintenance on the valve or its operator by measurement of stem travel when the ECCS subsystems are required to be OPERABLE.

HPSI SYSTEM Valve Number Valve Number MOV-616 MOV-617 MOV-626 MOV-627 MOV-636 MOV-637 MOV-646 MOV-647 l

h. By performing a flow balance test during shutdown following completion of HPSI system modifications that alter system flow characteristics and verifying the following flow rates:

HPSI SYSTEM Single Pump 170 + 5 gpm to each injection leg.

i CALVERT CLIFFS - UNIT 1 3/4 5-Sa Amendment No.

1 EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

2. Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following completion of maintenance on the valve or its operator by measurement of stem travel when the ECCS subsystems are required to be OPERABLE.

HPSI SYSTEM Valve Number Valve Number MOV-616 MOV-617 MOV-626 MOV-627 MOV-636 MOV-637 MOV-646 MOV-647 l

h. By performing a flow balance test during shutdown following completion of HPSI system modifications that alter system flow characteristics and verifying the following flow rates:

HPSI SYSTEM 4

Single Pump 170 + 5 gpm to each injection leg.

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CALVERT CLIFFS - UNIT 2 3/4 5-Sa Arre n dmen t No .

ADMINISTRATIVE CONTROLS 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a. The facility shall be placed in at least HOT STANDBY within one hour.
b. The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour. The Manager - Nuclear Power Department and the OSSRC shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
c. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the POSRC. This report shall describe . (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems, or structures, and (3) corrective action taken to prevent recurrence.
d. The Safety Limit Violation Report shall be submitted to the Commisssion, the OSSRC, and the Manager - Nuclear Power Department within 14 days of the violation.

6.8 PROCEDURES 6.8.1 - Written procedures shall be established, implemented, and maintained covering the activities referenced below:

a. The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, 1978 Revision. l
b. Refueling operations.
c. Surveillance and test activities of safety-related equipment.
d. Security Plan Implementaion.
e. Emergency Plan Implementation.
f. Fire Protection Program Implementation.

6.8.2 Each procedure and administrative policy of 6.8.1 above, and changes thereto, shall be reviewed by the POSRC and approved by the Plant Superintendent prior to implementation and reviewed periodically as set forth in administrative procedures.

CALVERT CLIFFS - UNIT 1 6-13 Amendment No.

PROPOSED CHANGE TABLE 3.7-4 SAFETY-RELATED HYDRAULIC SNUBRERS*

SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICUI.T 9 NUMBER ON, LOCATION AND ELEVATION INACCESSIBLE ZONE ** TO REMOVE (A OR 1) (YES OR NO) (YES OR NO) en i 1-83-40 MS FROM SG //12 TO AFW PUMP A No No g 27' M l-83-40 A MS FROM SG //12 TO AFW PUMP A No No

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27' 1-83-41 AFW PUMP ISOLATION VALVE BYPASS A No No 27' l-83-44 STEAM SUPPLY TO AFW PUMP 27' A No No 1-83-47 AFW PUMP ISOLATION VALVE BYPASS A No No

,y 27' l-83-48 AFW PUMP ISOLATION VALVE BYPASS A No No 27' l-83-49 MAIN STM LINE ENCAPSULATION 27' A No Yes l l-83-50 M AIN STM LINE ENCAPSULATION 27' A No Yes 1-83-51 MAIN STM LINE ENCAPSULATION 27' A No Yes 1-83-52 MAIN STM LINE ENCAPSULATION 27' A No Yes 1-83-53 MAIN STM LINE ENCAPSULATION 27' A No Yes

( l-83-54 MAIN STM LINE ENCAPSULATION 27' A No Yes E

.F

CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITIdN FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:

a. An overall integrated leakage rate of:
1. 1La (346,000 SCCM), 0.20 percent by weight of the containment air {

per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at Pa ,50 psig, or

2. 1Lt (61,600 SCCM), 0.058 percent by weight of the containment air j 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 Pt ,25 psig.
b. A combined leal'we rate of < 0.60 La (207,600 SCCM), for all penetrations l and valves subject to Type B and C tests when pressurized to Pa.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With either (a) the measured overail integrated containment leakage rate exceeding 0.75 La (259,500 SCCM) or 0.75 Lt (46,200 SCCM), as applicable, or (b) with the measured combined leakage rate for all penetrations and valves subject to Types B and C tests exceeding 0.60 La , restore the leakage rate (s) to within the limit (s) prior to increasing the Reacte- Coolant System temperature above 200 F.

SURVEILLANCE REOUIREMENTS l 4.6.1.2 The containment leakage rates shall be demonstrated at the following test

! schedule and shall be determined in conformance with the criteria specified in Appendix 3 of 10 CFR 50 using the methods and provisions of ANSI N45.4 - 1972:

a. Three Type A tests (Overall Integrated Containment Leakage Rate) shall be conducted at 40 10 month intervals during shutdown at either Pa (50 psig) or at P t(25 psig)2during each 10-year service period. The third test of each i

set shall be conducted during the shutdown for the 10-year plant inservice inspection.

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CALVERT CLIFFS - UNIT 1 3/46-2 Amendment No.

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CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:

a. An overall integrated leakage rate of:
1. 1L (346,000 SCCM), 0.20 percent by weight of the containment air l per E4 hours at Pa ,50 psig, or
2. 1Lt (44,600 SCCM), 0.058 percent by weight of the containment air l 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 Pt ,25 psig.
b. A combined leakage rate of 10.60 La (207,600 SCCM), for all penetrations l and valves subject to Type B and C tests when pressurized to Pa.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With either (a) the measured overall integrated containment leakage rate exceeding 0.75 La (259,500 SCCM) or 0.75 Lt (33,400 SCCM), as applicable, or (b) with the measured combined leakage rate for all penetrations and valves subject to Types B and C tests exceeding 0.60 La , restore the leakage rate (s) to within the limit (s) prior to increasing the Reactor Coolant System temperature above 200 F.

SURVEILLANCE REOUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria specified in Appendix 3 of 10 CFR 50 using the methods and provisions of ANSI N45.4 - 1972:

a. Three Type A tests (Overall Integrated Containment Leakage Rate) shall be I

conducted at 40 + 10 month intervals during shutdown at either Pa (50 psig) or at P t(25 psig) during each 10-year service period. The third test of each set shall be conducted during the shutdown for the 10-year plant inservice inspection.

CALVERT CLIFFS - UNIT 2 3/46-2 Amendment No.

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CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

b. If any periodic Type A test fails to meet either .75 La or .75 L t, the test schedule for subsequent Type A tests shall be reviewed and approved by the Commission. If two consecutive Type A tests fail to meet either .75 La or

.75 L t, a Type A test shall be performed at least every 18 months until two consecutive Type A tests meet either .75 aL or .75 L1 at which time the above test schedule may be resumed.

c. The accuracy of each Type A test shall be verified by a supplemental 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 (86,500 SCCM) or 0.25 Lt(15,400 SCCM). l
2. Has a duration sufficient to establish accurately the change in leakage between the type A test and the 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 no greater than 24 months except for tests involving air 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.

CALVERT CLIFFS - UNIT 1 3/46-3 Amendment No.

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1 CONTAINMENT SYSTEMS S_UR'!EILLANCE REOUIREMENTS (Continued)

b. If any periodic Type A test falls to meet either .75 La Of '75 Lt ,the test schedule for subsequent Type A tests shall be reviewed and approved by the Commission. If two consecutive Type A tests fall to meet either .75 La or

.75 L t, a Type A test shall be performed at least every 18 months until two consecutive Type A tests meet either .75aL or .75 Lt at which time the above test schedule may be resumed,

c. The accuracy of each Type A test shall be verified by a supplemental 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(86,500 SCCM) or 0.25 L t(11,100 SCCM). I
2. Has a duration sufficient to establish accurately the change in leakage between the type A test and the 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 greaterBthan and24C months tests shall be for except conducted with gas tests invetving air at P locks.(50 psig) at intervals

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.

CALVERT CLIFFS - UNIT 2 3/46-3 Amendment No.

CONTAINMENT SYSTEMS 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 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 of10.05 La (17,300 SCCM) at Pa, 50 psig. l APPLICABILITY: MODES 1,2,3 and 4.

g ACTION:

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a. With an air lock inoperable, exce'pt 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 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 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 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.* Af ter 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 La (69.2 SCCM) as determined by precision flow measurement l when the volume between the door seals is pressurized to a constant pressure of 15 psig,

CALVERT CLIFFS - UNIT 2 3/46-4 Amendment No.

CONTAINMENT SYSTEMS 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 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 of10.05 L a(17,300 SCCM) at Pa, 50 psig. l 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 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 an air lock inoperable due to an inoperable door gasket:
1. Maintain the remaining door of the affected air %k 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 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.* 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 La (69.2 SCCM) as determined by precision flow measurement l when the volume between the door seals is pressurized to a constant pressure of 15 psig,

CALVERT CLIFFS - UNIT 1 3/46-4 Amendment No.

-- . . _. . _ _ - ~ -_ -__ __. . . _._ . . . . . - . _- - - _ . - ._

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CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) ,

i 4.6.4.1.2 Each isolation valve specified in Table 3.6-1 shall be demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 months by: ,

a. Verifying that on each containment isolation Channel A or Channel B test signal, each required isolation valve actuates to its isolation position.  !
b. Verifying that on each Containment Radiation-High Test Channel A or Channel B test signal, both required containment purge valves actuate to
their isolation position.

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! c. Verifying that on each Safety injection Actuation Channel A or Channel B

! test signal, each required isolation valve actuates to its isolation position.

4.6.4.1.3 The isolation time of each power operated or automatic valve of Table ,

l 3.6-1 shall be determined to be within its limit when tested pursuant to Technical j Specification 4.0.5.

4.6.4.1.4 Containment purge isolation valves shall be demonstrated OPERABLE at ,

l least once every 6 months 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 0.60 L a i

(207,600 SCCM). The leakage rate for the containment purge isolation valves shall also l ,

be compared to the previously measured leakage rate to detect excessive valve l degradation.

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, CALVERT CLIFFS - UNIT 2 3/4 6-18 Amendment No.

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CONTAINMENT SYSTEMS, SURVEILLANCE REQUIREMENTS (Continued) 4.6.4.1.2 Each isolation valve specified in Table 3.6-1 shall be demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 months by:

a. Verifying that on each containment isolation Channel A or Channel B test signal, each required isolation valve actuates to its isolation position.
b. Verifying that on each Containment Radiation-High Test Channel A or Channel B test signal, both required containment purge valves actuate to their isolation position.
c. Verifying that on each Safety injection Actuation Channel A or Channel B test signal, each required isolation valve actuates to its isolation position.

4.6.4.1.3 The isolation time of each power operated or automatic valve of Table 3.6-1 shall be determined to be within its limit when tested pursuant to Technical Specification 4.0.5.

4.6.4.1.4 Conta!nment purge isolation valves shall be demonstrated OPERABLE at least once every 6 months 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 0.60 L a (207,600 SCCM). The leakage rate for the containment purge isolation valves shall also l be compared to the previously measured leakage rate to detect excessive valve degradation.

CALVERT CLIFFS - UNIT 1 3/46-18 Amendment No.

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