ML20138C879

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Proposed Tech Specs Re Conversion of Reactor Bldg Standby Ventilation Sys low-range Noble Gas Radiation Monitor to Vent Stack low-range Nobel Gas Radiation Monitor
ML20138C879
Person / Time
Site: Shoreham File:Long Island Lighting Company icon.png
Issue date: 10/21/1985
From:
LONG ISLAND LIGHTING CO.
To:
Shared Package
ML20138C871 List:
References
NUDOCS 8510230086
Download: ML20138C879 (3)


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O ACCIDINT MONITORING INSTRUMENTAT10N

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c/ e REQUIRLD NUMBER CllANNLl5

'E' c INSTRUMENT OF CilANNits OPE Rant'E ACil0N e, z -

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1. Reactor viessel Pressure 2 1 80

, 2. Reactor Vessel Water Level 2 1 80

3. ' Suppression Pool Water Level ,.

2 1 80- h

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4. Suppression Pool Water Temperature 2/ sector 1/ sector 80 -f g

i' 5. Drywell Pressure 2 1 80 Q hiz;. 6. Drywell Air Temperature I

w 1 1 80 in 1

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27. .' ; w 7. Drywell and Suppression Chamber Oxygen Concentration 2 1 80 M c'.

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" 8. Drywell and Suppression Chamber ifydrogen Concentration h j Analyzer and Monitor 2 1 80 3

9. Safety / Relief Valve Position Indicators 1/ valve 1/ valve 80
10. Primary Containment Gross Radiation Monitors 2 1 81 Q

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11. High Range Plant Vent Stack
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12. liigh Range. Reactor 81dg. Standby Ventilation System
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7 13. Low Range Reactor Bldg. Standby Ventilation System

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if (d) Eme.cency nesperse Capabilities (r4ncric tctter 82-33, Suppler.ent 1 to '.UREG-0737) y The licensee sF-ll complete emergency response facilities and capabilities a required in Attachmerit 1 ' this licerse.

(8) _Ecuipnent Qualifie iori (Section 3.11, SSER7' Prict te ':over-ber-30r-498E/the licensee shall ctvircnraer. tally qualify all electrical equipment according to the provisiens of 10 CFh 50.49.

j'_ p+ b MueAW 30,1995

,f(9)

Instrumentation and Controls Systers Recuired for Safe Shutdcwn j M ection 7.4.3_SSER3, SSER4, SSER 8)

Prior to startup following the first refueling outage, the licensee

f. shall implement.and docutent all of the required design changes

,i ciscussed in Attachment 4 and shall perforn an acceptable procedure

verification test for the rencte shutdown system design.

I f (10) Cor. crete and Structural Steel Internal Structures (Section 3.8.2 SER, SSER1, SSEk3, SSER4) g The licersee shall not operate the residual heat removal (RHR) system in the steam conder. sing mode (SCM) during any norr.al plart cperations. However, the SCh may bt. used, in accordance with the provisions of 10 CFR 50.54 (x) and (y), as a last resort when all cther meens of core or containment cooling have bcen lost.

(11) SSER4, Containment SSER 8) Isclation System (Section 6.2.3 SER,'SSER1, SSER3, 1

I Prior to start-up following the first rafueling outage the licer.see

\ shall install two isolation barriers in series in all instrument f i lines penetrating containment that are not part of the automatic j

\ reactor protection systen. Proposals from the litersee cr. how

\ this shall be accomplished as well as details en the necessary j

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cesign changes, shall be submitted for liRC staff review and approval.

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