ML17291A478

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Proposed Tech Spec 3/4.1.3.1, Reactivity Control Sys.
ML17291A478
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 10/31/1994
From:
WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:
Shared Package
ML17291A477 List:
References
NUDOCS 9411080149
Download: ML17291A478 (8)


Text

BLUEST FOR AMENDMENTTO 3/4.1.3.1, "REACTIVITYCONTROL SYSTEMS" Attachment 3 TECHNICAL SPECIFICATION PAGES WITH PROPOSED CHANGES INDICATED 94ii080i49 94i03i PDR ADOCK 05000397 P ~

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REQUEST FOR AMENDMENTTO 3/4.1.3.1, "REACTIVITYCONTROL SYSTEMS" Attachment 3 INSERT 1 d.>> With one or more SDV vent or drain line with one valve inoperable,

1. Isolate'¹ the associated line within 7 days.
2. Otherwise, be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

e.>> With one or more SDV vent or drain lines with both valves inoperable,

1. Isolate'>> the associated line within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
2. Otherwise, be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

INSERT 2

<<Separate ACTION statement entry is allowed for each SDV vent and drain line.

<<<<An isolated line may be unisolated under administrative control to allow draining and venting of the SDV.

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REACTIVITY CONTROL SYSTEMS LIMITING CONOITION FOR OPERATION (Continued ACTION (Continued) a) Electrically, or b) Hydraulically by closing the drive water and exhaust water isolation valves.

2. If the inoperable control rod(s) is inserted, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, disarm the associated directional control valves"" either:

a) Electrically, or b) Hydraulically by closing the drive water and exhaust water isolation valves.

Otherwise, be in at least HOT SHUTCOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

add XaSd.rk 1 3. The provisions of Specification 3.0.4 are not applicable.

C. With more than eight control rods inoperable, be in at least HOT SHUTCOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

SURVEILLANCE RE UIREMENTS

4. 1.3.1. 1 The scram discharge volume drain and vent valves shall be demonstrated OPERABLE by:
a. At least once per 31 days verifying each valve to be open,~ and
b. At least once per 92 days cycling each valve through at least one complete cycle of full travel.

4.1.3. 1.2 When above the low power setpoint of the RWM and RSCS, all withdrawn control rods not required to have their directional control valves disarmed electrically or hydraulically shall be demonstrated OPERABLE by moving each control rod at least one notch: ,o~

a. At least once per 7 days, and go ~
b. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when any control rod is immovable as a po9 result of excessive friction or mechanical interference.
4. 1.3.1.3 All control rods shall be demonstrated OPERABLE by performance of Surveillance Requirements 4. 1. 3. 2, 4. 1. 3.4, 4. 1. 3. 5, 4. 1. 3. 6, and 4. 1. 3. 7.

Add

~54rf' "These valves may be closed intermittently for testing under administrative control s.

""May be rearmed intermittently, under administrative control, to permit testing associated with restoring the control rod to OPERABLE status.

WASHINGTON NUCLEAR - UNIT 2 3/4 1-4

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REACTIVITY CONTROL SYSTEMS SURVEILLANCE,RE UIREMENTS (Continued)

4. 1.3. 1.4 The scram discharge volume shall be determined OPERABLE by demonstrating:
a. The scram discharge volume drain and vent valves OPERABL mhen-ntrol~od~e-swam-4es4ed from-a-.noma-l-con&A md-conf4gur-HIS-RGMIBI&l'I%

18 months by verifying that the drain and vent valves:

1. Close ithin 30 seconds after receipt of signal for control rods to scram, and 3w. hc. uh ov'&nnula'fly
2. Open when the sera i nal is et.

ar Semor b+

b. Proper float response by performance of a CHANNEL FUNCTIONAL TEST of the scram discharge volume scram and control rod block level instru-mentation after each scram from a pressurized condition.

e-prov+a-'iens-of Speci-fica&on-4-.0A ave-not-app-l-i-caber e~.-y iw4o-

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-GPERATNNAh-GQNNTKN-2 tv-i-ded-@he-surveW+ance-i~p~rmed~Am-g-I BN-BIB-BEHIR~

WASHINGTON NUCLEAR - UNIT 2 3/4 1-5

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