ML19343B035
| ML19343B035 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 11/03/1980 |
| From: | Harriston W ALABAMA POWER CO. |
| To: | |
| Shared Package | |
| ML19343A898 | List: |
| References | |
| FNP--EIP-6-1, FNP-0-EIP-6-01, NUDOCS 8011240508 | |
| Download: ML19343B035 (8) | |
Text
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O VOL. 14 FNP-0-EIP-6
-October 6, 1980 Revision 2 FARLEY NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE FNP-0-EIP-6 S
A F
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Y TECHNICAL SUPPORT TO TEE EMERGENCY PLAN R
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ESONAL FRIVACY I!TFCEMATION DEI.ETED IN ACCORDANCE WITH THE mcx or In cmTION ACT Approved:
L 0. J. (1=M_ &
Plant Manager Date Issued:
I t rc Date of Implementation: _11-17-80 Disk EIP-3 List-o f-Effective-Page Page Rev. W 1-3 Rev. 2 DCCUtA?NT CONTROL App. 1,2 Rev. 2 CCNTROLLED COPY Tbl. 1,2 Bev. 2 DO NOT REPRODUCE COPY NO. 039 80fI M o Sc8 y
VOL. 14 FNP-0-EIP-6 TECHNICAL SUPPORT TO THE EMERGENCY PLAN
. l.0 Purpose This procedure delineates the responsibilities of the Technical and Systems Performance Group during emergencies l at the Farley Nuclear Plant.
2.0 References 2.1 Joseph M. Farley Nuclear Plant Emergency Plan 2.2 FNP Operating Manual, Vol. 14, FNP-0-EIP-8, Notification Procedure 4
2.3 FNP Operating Manual, Vol. 14, FNP-0-EIP-9, Radiation Exposure Estimation and Classification of Emergencies.
2.4 FNP Operating Manaul, Vol. 14, FNP-0-EIP-10, i
Evacuation and Personnel Accountability.
3.0 General 3.1 Technical support during emergencies shall consist of but is not limited to the following actions:
3.1.1 Maintain communications between the TSC, EOF, NRC, and other off-site authorities.
3.1.2 Maintain a chronological log of all off-site communications for the duration of the emergency.
3.1.3 Verify initial radiation dose calculations and continuously update the assessment of off-site doses.
3.1.4 If off-site dose assessments are required, maintain surveillance of the radiological and meteorological monitors in the 7ontrol room.
3.1.5 Provide engineering support to the Emergency Director.
3.1.6 Establish the plant parameters remote monitoring capability in the TSC.
3.2 All personnel assigned to the technical group shall report to the service building auditorium in accordance with FNP-0-EIP-10, Evacuation and Personnel Accountability, in the event of an emergency.
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VOL. 14 FNP-0-EXP-6 4.0 Procedure 4.1 The Technical Manager shall:
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4.1.1 Assign an engineer to be responsible for off-site communications and for logging all off-site communications.
4.1.2 Assign an engineer to maintain surveillance of the radiological and meteorological monitors in the control rocm and to verify and update off-site dose assessments.
4.1.3 Assist the Emergency Director by providing engineering support for assessing, mitigating and/or recovering from the emergency.
4.1.4 Upon direction from the Emergency Director, establish the plant parameter remote monitoring capability per Appendix 1.
4.2 The engineer who is assigned communications responsibilities shall:
4.2.1 Report to the location of the Emergency Director upon instructions'from the Emergency Director or the Technical Manager.
4.2.2 Establish and maintain at least one communications link with the Emergency Coordinator.
Refer to FNP-0-EIP-8, Notification Roster.
4.2.3 Establish communications wiC other off-site authorities as directed by the l
l Emergency Director.
Refer to FNP-0-EIP-8, Noti:ication Roster.
4.2.4 Maintain a chronological log of all off-site communications noting the organization contacted and a summary of the conversation.
4.3 The engineer who is assigned dose assessme t responsibilities shall:
4.3.1 Report to the control rocm upon instructions from the Emert.ency Director or the-Technical Man ger.
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VOL. 14 FNP-0-EIP-6 4.3.2 Verify the correctness of the initial off-site dose calculations.
Refer to FNP-0-EIP-9, Radiation Exposure Estimation and Classification of Emergencies.
4.3.3 Maintain surveillance of the radiological and mcteorological monitors in the control room.
4.3.4 Periodically or upon instructions from the Emergency Director or the Health Physics Manager, reassess the off-site l
dose estimation based on data from the radiological and meteorological monitors or on-site /off-site survey data available from the Health Physics Manager.
4.3.5 Report the results of dose assessments to the Emergency Director and the Health Physics Manager.
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1 FNP-0-EIP-6 APPENDIX 1 PLANT PARAMETER REMOTE MONITORING CAPABILITY IN THE TECHNICAL SUPPORT CENTER 1.0 Activation of Remote Monitoring Capability 1.1 The Emergency Director shall direct one of-the-personnel in the TSC to set up an available plant computer CRT for monitoring purposes by TSC personnel.
1.2 Perform the following steps to reposition the computer console CRT (computer device #14) for monitoring by TSC personnel:
1.2.1 Disconnect the power cable and the red, green, and blue signal co-ax cables from the rear of the CRT (inside console housing).
1.2.2 Roll the CRT out of the rear of the console housing and position at desired location as directed by the Emergency Director.
1.2.3 Connect the " control rocm" end of the co-ax signal extensions cables and power feed cable to the existing color signal cables and power feed cable in the comcuter console (extension cables are located in control room overhead).
1.2.4 Connect the "TSC" end of the co-ax extension cables and power feed cable to the remotely located CRT.
1.2.5 Depress the "CRT" function pushbutton.
1.2.6 Depress the "1" and then "6" numeric pushbuttons.
1.2.7 Depress the "VALUE 1" pushbutton.
1.2.8 Depress the "2" numeric pushbutton.
1.?.9 Depress the "VALUE 2" pushbutton.
1.2.10 Depress the " START" pushbutton.
1.2.11 Verify all parameters listed in Table 1 appear on the CRT.
1 Appendix l' i
Page 1 of 2 Rev. 2 j
FNP-0-EIP-6 2.0 Deactivation of Remote Monitoring Capability Perform the following steps to reposition the' remote CRT back in the ccmputer console:
-2.1 Disconnect the power cable and co-ax extension cables from the rear of the CRT and from the computer console.
"2 Roll the CRT into the rear of the console and reconnect the co-ax and power' cables.
2.3 Perfora steps 1.2.5 - 1.2.10.
2.4 Place the co-ax and cower extension cables in the control room ove'rhead.
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Appendix 1 Page 2 of_2 Rev. 2 w,
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FNP-0-EIP-6
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TABLE 1 STEAM GENERATOR TUEE RUPTURE MONITORING PARAMETERS COMPUTER ADDRESS PARAMETER
_0480A-PRESSURIZER LEVEL (1)
LO481A PRESSURIZER LEVEL (2)
P0480A PRESSURIZER PRESS (1)
P0481A PRESSURI M PRESS (2)
P0499A RCL SYS m PRESS U0090 HOTTEST THERMOCOUPLE T0419A RCL 1 WIDE RNG HOT LEG T T0406A RCL 1 WIDE RNG COLD. LEG T LO403A STM GEN 1 WIDE RNG LEVEL P0400A STM GEN 1 STM OUT PRESS T0439A RCL 2 WIDE RNG HOT LEG T T0426A RCL 2 WIDE RNG COLD LEG T LO423A STM GEN 2 WIDE RNG LEVEL t
PO420A STM GEN 2 STM CUT PRESS T0459A RCL 3 WIDE RNG HOT LEG T, T0446A RCL 3 WIDE RNG COLD LEG T LO443A
'STM GEN 3 WIDE RNG LEVEL P0440A STM GEN 3 STM OUT PRESS P1000A CONTAINMENT (1) PRESS P1001A CONTAINMEYr (2) PRESS R0011A CONTAINMENT AIR PARTICLE R R0012A CONTAINMENT GAS R Table 1 Page 1 of 2 Rev. 2
FNP-0-EIP-6 TABLE 1 (con't)
COMPUTER ADDRESS PARMETER R0019A STM GEN BLOWDOWN DRAIN R R0021A VENT AIR PARTICLE R R0015A STEAM AIR EJECTOR E'GL-1UST R R0050A GROSS FAILED FUEL DETECTOR Table 1 Page 2 of 2 Rev. 2
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