ML20083D662

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Proposed Tech Spec 3/4.9.6.1 Re Refueling Platform for NF500 Main Hoist Grapple Mast
ML20083D662
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 09/25/1991
From:
ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20083D658 List:
References
NUDOCS 9110010131
Download: ML20083D662 (3)


Text

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N P E - 91/o 3 REFUELING OPERATIONS 3/4.9.6 REFUEllNG EQUIPMENT REFUELING PLATFO'RM --

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MMITINGCONDITIONFOROPERATION N'% h foho ding  %

3.9.6.1 The refueling p shall be used for handitr,latform shail be OPERABLE and only the main boist

- fuel assembliesg:

(r APPLICABILITY: During ha dling of fuel assemblies or control rods in the 7 primary containment with the refueling platform.

ACTION:

1

(

With the requirements for refueling platform OPERABILITY not utisfied, h suspend use of any inoperable refueling platform equipment from operations involving the handling of fuel assemblies or control rods after placing the load in a safe conditien.

SURVEILLANCE REQUIREMENTS 4.9.6.1 Each refueling pictform hoist to be used for handling fuel assemblies or control rods shall be demonstrated OPERABLE within 7 days prior to the handling of fuel assemblies or control rods:

a. In the containment fuel pool, reactor cavity or reactor pressure vessel by:
1. Demonstrating oparation of the slack cable cutoff on the main hoist wh w the total cable load is 50110 pounds.

,  ? Damonstrati.'g operation of the grapple engaged loaded interlock o the main hoist before the total cabi d_egte 4354ounds. 1 3.

75 0(535 Demonstrating ope.ation of the jam cutof on a n hoist before the total cable load exceeds 425 Fpounds. l t._ i9 3 o ( m.5 0)4

4. Demonstrating operation of primary (and redundant overload cutof f on the auxiliary hoists before the load exceeds 550 pounds,
b. In or over the reactor pressure vessel by:
1. Demonstrating operation of the downtravel cutoff on the main hoist 'when the bottom of the grapple is > 1.0 inch above the top guide. ,
2. Demonstrating operation of the primary and redundant fuel load .

interlocks on the main hoist before t.he total c ble load exceeds 75c(.roOOI 60Fpounds.

p bk*kObh $bO$hU FDR CRAND GULF-UNIT 1 3/4 9-8 Amendment No. 55,

l l -

INSERT A

a. NF-500 mast, or
b. NP-400 mast INSERT B
  • When the NF-400 mast is in use, setpoints in () apply for these surveillance requirements.

Inserts for TS page 3/4 9-8

PE -9\/03 3/4.9 REFUELING OPERATIONS BASES -

3/4.9.1 REACTOR MODE SWITCH Locking the OPERABLE reactor mode switch 'n the Shutdown or Refuel position, as specified, ensures that the restrictions on control rod withdrawal and refueling platform movement during the refueling operations are properly activated. These conditions reinforce the refueling procedures and reduce the probability of inadvertent criticality, damage to reactor internals or fuel assemblies, and exposure of personnel to excessive radioactivity.

3/4.9.2 INSTRUMENTATION g

The OPERABILITY of at least two source range monitors ensures that redundant monitoring of the core, capability is available to detect changes in the reactivity condition y 3/4.9.3 CONTROL R00 POSITION The requirement that all control rods be inserted during other CORE ALTERATIONS rod. ensures that f uel will not be loaded into a cell without a control 3/4.9.4 DECAY TIME The minimum requirement for reactor subcriticality prior to fuel movement ensures short lived that sufficient fission products. time has elapsed to allow tne radioactive decay of the tions used in the accident analyses.This decay time is consistent with the assump-3/4.9.5 COMMUNICATIONS The requirement for communications capability ensures that refueling station personnel can be promptly informed of significant changes in the facility status or vessel. core reactivity condition during movement of fuel within the reactor pressure 3/4.9.6 REFUELING. EQUIPMENT The OPERABILITY requirements ensure that (1) only the main hoist of the refueling platform or the main hoist of the fuel handling platform will be used for handling fuel assemblies within the reactor pressure vessel, (2) platform hoists have sufficient load capacity for handling fuel assemblies and/or control rods,-amF{3) lifting fo the core internals and pressure vessel are protected from excessive l h

i event _they are_jnadvertently en aged _durinq 1 fi n operation y an 1 (q). a .f u.c\ ban di e i5 PWTNC\ e ham u.cusA G %,

3 G e c e.

in -h evtce -_i t b a ce mu skG d u Mn 3 \M M3 ope.raMorn.

GRAND GULF-UNIT 1 B 3/4 9-1 p mnf m eni N c, .

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