ML20094J670
| ML20094J670 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/08/1984 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20094J662 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-2.F.1, TASK-TM NUDOCS 8408140415 | |
| Download: ML20094J670 (2) | |
Text
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TNEE A.1-1 IOSI RUME31 SU;VEILLANCE RCg!!RENCUTS
' vmo bg CuAmste_ ot sC Ra rr ion CucCr TIS CAtleRATC RcnARuS Uf$
1.
Protectlen Channel NA M
NA I
Coincidence Legle 2.
Centrol Red Drive O
NA M
$A wlm twWdW htd i
Trip Breewer
[ utCD undervoltage trip features.
@g 3.
Power Range Anp11rler D(1)
NA (2) otn f h$$$
! 2'O
{
helence check once per ohlf t. Nedt Selence estibration ehe!! he performed ebenever beet i
{
belance suceede Indiested neutron poser by A.
Power Range Channel aere then two percent.
5 N
M(1)(2)
(1) When reacter power le greater then 408 l
i am Os verify labelence weing incere-instrumentation.
I
}
(2) When ebeve ISS reacter power celeutete estal offset upper and lower ebenbere efter each startup af not done within the previews 5.
Intermediate Range Channel 5(1)
P NA (1) When in service.
seven doye.
I, 6.
Sewece Range Channet S(!)
P NA j
7 Roseter Ceekent Temperature S
M R
(1) When in service.
Channe!
S.
High Reacter Coelant S
M R
Pressure Channel j
9.
Lew Reector Coelant
}
hI Pressure Channel.
S M
R
- 4e
=
0 I
1 i
1 1
l
documentation that the changes have been reviewed and c.
~
approved pursuant to 6.8.2.
Shall become effective ipon review and approval by GPUNC 2.
Management.
6.14 (FFSITE DOSE CALCt1ATICH MAWAL (ODCN) 6.14.1 The ODCM shall be approved by the Commission prior to' implementation.
6.14.2 GPU W clear Corporation initiated changes to the 00CM:
1.
Shall be submitted to the MC in the Semiannual Radioactive Effluent Release Report for the period in which the changes were made.
This submittal shall contain:
sufficiently detailed information to justify the changes without a.
benefit of additional or s@plemental information; b.
a determination that the changes did not reduce the accuracy or reliability of dose calculations or setpoint determinations; and, l
c.
documentation that the changes have been reviewed and approved pursuant to 6.8.2.
4 2.
Shall become effective won review and approval by GPUNC Management.
6.15 Osleted i
6.16 Post-Accident Sanclino Procrams NUREG 0737 (II.8.3, II.F.1.2)
Programs which will ensure the capability to ac.urately sample and analyze vital areas under accident conditicos have been inplemented.
The following programs have been established:
1.
Iodine Sampling and Particulate Sanpling 2.
Reactor Coolant Sangling 3.
Containment Atmosphere Sampling i
Each program shall be maintained and shall include the following:
1.
Training of personnel, 2.
Procedwes and, 3.
Provisions for maintenance of sagling and analysis equipment.
6 9
5 6-22 4
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