ML20211E025

Proposed Tech Spec Deferring Performance of Insp & Operability Testing of Reactor Vessel Internal Vent Valves to Coincide W/Next Reactor Vessel Head Removal No Later than Cycle 5 Refueling Outage

ML20211E025
Person / Time
Site:	Davis Besse
Issue date:	06/06/1986
From:	TOLEDO EDISON CO.
To:
Shared Package
ML20211E022	List: ML20211E017 ML20211E025
References
TAC-61699, NUDOCS 8606130198
Download: ML20211E025 (5)

Text

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REACTOR COOLANT SYSTEM PRESSURIZER LIMITING CONDITION FOR OPERATION 3.4.9.2 The pressurizer temperature shall be limited to:

a. A maximum heatup and cooldown of 100'F in any one hour period,

b. A maximum spray water temperature differential of 410*F, and

c. A minimum temperature of 120'F when the pressurizer pressure is > 625 psig.

APPLICABILITY: At all times.

ACTION:

With the pressurizer temperature limits in excess of any of the above limits, restore the temperature to within limits within 30 minutes; perform an engineering evaluation to determine the effects of the out-of-limit condition on the fracture toughness properties of the pressurizer; determine that the pressurizer remains acceptable for continued operation 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 reduce pressurizer pressure to less than 500 psig, 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 4.4.9.2 The pressurizer temperature shall be detemined to be within the limits at least once per 30 minutes during system r.satup or cooldown. The spray water temperature differential shall be determined to be within the limit once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during spray operation with pressurizer temperature

> 440'F.

8606130198 860606 PDR ADOCK 05000346 P PDR DAVIS-BESSE, UNIT 1 3/4 4-29 I

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l REACTOR COOLANT SYSTEM FOR INFORMATION ONLY 3.4.10 STRUCTURAL INTEGRITY ASME CODE CLASS 1, 2 and 3 COMP 0NENTS t

. LIMITING CONDITION FOR OPERATION l 3.4.10.1 The structural integrity of ASME Code Class 1, 2 and 3 components shall be maintainea in accordance with Specification 4.4.10.1.

APPLICABILITY: All MODES.

ACTION:

a. With the structural integrity of any ASME Code Class 1 component (s) not confnrming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or

isolate the affected component (s) prior to increasing the Reactor l Coolant System temperature more than 50*F above the minimum temperature required by NDT considerations.

b. With the structural integrity of any ASME Code Class 2 component (s) not conforming to the above requirements, restore the structural l

integrity of the affected component (s) to within its limit or isolate the affected component (s) prior to increasing the Reactor j .

Coolant System temperature above 200*F.

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! c. With the structural integrity of any ASME Code Class 3 component (s) not conforming to the above requirements, restore the structural integrity of the component (s) to within its limit or isolate the

, affected component (s) from service.

d. The provisions of Specification 3.0.4 are not applicable.

1 SURVEILLANCE REQUIREMENTS l

4.4.10.1 In addition to the requirements of Specification 4.0.5:

i a. The reactor coolant pump flywheels shall be inspected per the

! reconnendations of Regulatory Position C.4.b. of Regulatory

! Guide 1.14, Revision 1 August 1975.

l DAVIS-BESSE, UNIT 1 3/4 4-30

RkACORCOOLANT$YSTEM SURVETLLANCE REQUIREMENTS (Continued)

b. Each internals vent valve shall be demonstrated OPERABLE at least once per 18 months during shutdown.* by:

1. Verifying through visual inspection that the valve body

, and valve dise exhibit no abnormal degradation,

2. Verifying the valve is not stuck in an open positi5n, -

and

3. Verifying through manual actuation that the valve is fully open when a force of 1 00 4 lbs. is applied vertically upward.

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0 AVIS-BESSE. UNIT l- 3/4 4-31 Amendment No. 23

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> REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM VE.VTS FOR INFORMATION ONLY LIMITING CONDITION FOR OPERATION .

i 3.4.11 The fo11owing reactor coolant systes vent paths shall be oper-able-l

a. Reactor Coolant Systes Loop 1 with vent path through valves RC 4608A and RC 46088.

b. Reactor Coolant System Loop 2 with vent path through valves RC 4610A and RC 46108.

c. Pressuriser; with vent path through' EITHER valves RCll and RC2 (PORV) OR valves RC 239A and RC 200.

APPLICABII.ITY: Modes 1, 2 and 3 ACTION:

a. With one of the above vent paths inoperable, restore the inoperable vent path to OPERABLE status within 30 days, or, be in HOT STAND 8Y within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN i 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 two of the above vent paths inoperable, restore at .

least one of the inoperable vent paths to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT STAND 8Y within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHITTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

c. With three of the above vent paths inoperable, restore at least two of the inoperable vent paths to OPERABLE status a within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT STANDBY within 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 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

d. The provisions of specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.4.11 Each reactor coolant systee vent path shall be demonstrated CPERABLE at least once per 18 sonths by:

1. Verifying all manual isolation valves in each vent path '

are locked in the open position, and i 2. Cycling each valve in the vent path through at least one complete cycle of full travel from the control room during l

COLD SHUTDOWN or REFUELING, and I

l 3. Verifying flow through the reactor coolant vent system vent I patha during COLD SHUTDOWN or REI1JELING.

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DAVIS-BESSE, UtlIT 1 3/4 4-32 Amend. ment No. 85

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REACTOR COOLANT SYSTEM FOR INFORMATION ONLY BASES 3/4.4.10 STRUCTURAL INTEGRITY -- - - -- - The inspection prograns 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.

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

3/4.4.11 HICH POINT VENTS -

The Reactor Coolant System high point vents are installed per NtDLEG-0737 ites II.B.1 requirements. The operability of the system ensures capability of venting stess or noncondensable gas bubbles in the reactor cooling system to restore natural circulation following a small break loss of coolant accident.

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DAV!$.8 ESSE, UNIT 1 83/44-13 Ar endment Nol 85 J