ML20065F584

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Proposed TS 3/4.4.12 Re Limiting Condition for Operation, Surveillance Requirements & Bases Section for Pilot Operated Relief Valve & Block Valve
ML20065F584
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 03/30/1994
From:
CENTERIOR ENERGY
To:
Shared Package
ML20065F580 List:
References
NUDOCS 9404110423
Download: ML20065F584 (4)
v • d • e


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.- Dockst Nu1bar 50-346 Lic:nzd Number NPF-3 Sarial Nu2bar 2211

- A t tachm'e n t ' '

' P g2 11F 'NDEX t*MIT"E COMOITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS -

SEC-'*N PAGE 3/4.4.4 P RE15U RI ZER. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 / 4 4- 5 3/4.4.5 STEAM GENERATORS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/ 4 4-6 i

3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE l Leakage Detecti on Sys tems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 4-13 Operational L eakage. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 4-15 ]

3/4.4.7 CHEMISTRY...................................'............. 3/4 4-17

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3/4.4.8 SPECIFIC ACTIV1TY. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/ 4 ' 4-20 l

3/4.4.3 PRESSURE / TEMPERATURE LIMITS i 1

Reactor Cool an t Sys ten. . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . 3/ 4 4- 24 P res s uri z ar. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/ 4 4- 29 I

3/4.4.10 STRUCTURAL INTEGRITY..................................... 3/4 4-30 l

3/4.4.11 REACTOR COOLANT SYSTEM VENTS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/ 4 4-32 3/4.Il112. '9' LOT @F-RATED Krt 16F Jswd App Mce.c {fAL.s!E, .yq;/h)3 3/a.5 EMERGENCY CORE C001.ING SYSTEMS (ECCS) .

3/4.5.1 CORE FLOODING TANK 3...................................... 3/4 5-1 3/4.5.2 ECCS SUBSYSTEMS - T L 280*F........................... 3/4 5-3 3/4.5.3 E'CCS SUBSYSTEMS - T < 2 80

  • F . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 / 4 5 3/4.5.4 BORATED WATER STORME TAM K. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 5-7 i

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DAVIS-BESSE. UNIT 1 V Mendment No.135 i

l 9404110423 940330 7 PDR ADDCK 05000346 p PDR ,

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Docket Nunbar 50-346 Licensa Numb 2r NPF-3 Sarial Number 2211 l i

Attachment Page 12 INDEX BASES l 1

PAGE SECTION

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3/4.0 AP P L I C AB I L I T Y . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/ 4 0- 1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 B0 RATION CONTR0L........................................ B 3/4 1-1 3/4.1.2 B0kATION SYSTEMS...........s......... .................. B 3/4 1-2 3/4.1.3 MOVABLE CONTROL ASSEMBLIES. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 1-3 .

3/4.2 POWER DISTRIBUTION LIMITS......................J........... B 3/4 2-1 3/4.3 INSTRUMENTATION l 3/4.3.1 and 3/4.3.2 REACTOR PROTECTION SYSTEM AND SAFETY SYSTEMS I NSTRUMENTATION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 3-2 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOL ANT L00PS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/ 4 4- 1 3/4.4. 2 and 3/4.4.3 SAFETY VALVES................................ B 3/4 4-1 3/4.4.4 PRESSURIZER............................................. B 3/4 4-2 3/4.4.S ST EAM GE N E RATO RS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3 / 4 4 - 2 3/4.4.6 REACTOR C00LAbR SYSTEM LEAKAGE. . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 4-4 3/4.4.7 CH E M I S T RY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3 / 4 4 - S 3/4.4.8 SPECIFIC ACTIVITY....................................... B 3/4 4-5 3/4.4.9 PRESSURE / TEMPERATURE LIMITS............................. B 3/4 4-6 3/4.4.10 STRUCTU RAL I NTEGRI TY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . -8 3/4 4- 13 3/4.4.11 HIGH P0 INT V ENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/ 4 4 - 13 3hh % s ;;L 140T (' PEOTF D BiTu Ci^ dALAE A+'O GLocx VA t-JE B3//fJP/3l DAVIS-BESSE. UNIT 1 II Amendment No.13S

Dockat Nu:bar 50-346 ,

.LicInsa Nurb'Ir NPF-3 S3 rial Nunbar.2211

.Attachmen.t Page-13 's REACTOR COOLANT SYSTEM. .

i PILOT OPERATED RELIEF VALVE AND BLOCK VALVE j i

LIMITING CONDITION FOR OPERATION 3.4.12 'The Pilot Operated Relief Valve (PORV) and its associated block valve shall be OPERABLE.  ;

APPLICABILITY: MODES 1, 2, and 3.

ACTION: a. With the PORV inoperable because of seat leakage,;within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> restore the PORV to OPERABLE status or close the PORY block valve.with power maintained to the block valves 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-HOT SHUTDOWN within the following.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b. With the P0RV inoperable due to causes-other than seat leakage:
1. Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the PORV to OPERABLE status or close the PORV block valve.
2. If the PORV block valve is closed to comply with ACTION b.1, restore the PORV to OPERABLE status within the following 7 days and reopen the block valve, or 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
c. With the block valve inoperable, within 7 days restore the block valve to OPERABLE status; ' othe rwis e , 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-HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />,
d. The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.4.12.1 In addition to the requirements of Specification 4.0.5, the PORV shall be demonstrated OPERABLE at least once per 18 months by operating the PORV through one complete cycle of full travel during MODES 3 or 4.

4.4.12.2 The PORV Block Valve shall be demonstrated OPERABLE at least once per 92 days by operating the valve through one complete cycle of full travel unless the. block valve is closed in order to meet the requirements of Specification 3.4.12 ACTION a. or b.

DAVIS-BESSE, UNIT 1 3/4 4-33 Amendment No.

, ,Dockst Nuxbsr 50-346 Lictnsa Numbsr NPF-3 S2 rial Nuxbsr 2211 Attachment Page 14 j REACTOR COOLANT SYSTEM BASES - ..

3/4.4.10 STRUCTURAL INTEGRITY The inspection programs for ASME Code Class 1, 2 and 3 components, except steam generator tubes, ensure that the structural integrity of these components will be maintained at an acceptable level'throughout the life of the plant. To the extent applicable, the inspection program for these components is in compliance with Section XI of the ASME Boiler and Pressure Vessel Code.

4 The internals vent valves are provided to relieve the pressure generated by steaming in the core following a LOCA so that the core remains suffi-ciently covered. Inspection and manual actuation of the incyrnals vent valves 1) ensure OPERABILITY, 2) ensure that, the valves are not stuck open during normal operation, and 3) demonstrates that the valves are fully 4 open at the forces equivalent to the differential pressures assumed in the safety analysis.

3 /4. .11 HIGH POINT VENTS J

The React:or Coolant System high point vents are installed per NUREG-0737 item II.B.1 requirements. The operability of the system ensures capability of venting steam or noncondensable gas bubbles in the reactor cooling system to restore natural circulation following a small break loss of co an accident.

3/4.4.12 PILOT OPERATED REllEF VALVE AND BLOCK VALVE The OPERABILITY of the PORV flow path ensures that challenges to the pressurizer code safety valves will be minimized by providing an alternate means of limiting RCS pressure excursions.

PORV seat leakage less than the limits of Technical Specification 3/4.4.6.2 Operational Leakage, do not require entry into Technical Specification 3/4.4.12, Pilot Operated Relief Valve and Block Valve.

In the event of an inoperable PORV, the OPERABILITY of the PORV Block Valve provides a means of isolating the PORV flow path thus assuring RCS integrity through this relief path.

If the PORV Block Valve is closed due to seat leakage, the PORV Block valve should remain energized to assure the PORV flow path remains available if needed for-the beyond - design basis feed and bleed cooling mode of operation. Feed and bleed cooling is not part of the licensing basis for the plant.

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l DAVIS-BESSE, UNIT 1 B 3/4 4-13 _ Amendment No. 85 j l

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