ML20070V687: Difference between revisions

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| number = ML20070V687
| number = ML20070V687
| issue date = 03/20/1991
| issue date = 03/20/1991
| title = Issue 55 to Abnormal Operating Procedure AOP-R, Loss of Access to Control Room. W/910405 Ltr
| title = Issue 55 to Abnormal Operating Procedure AOP-R, Loss of Access to Control Room
| author name = Fuller C
| author name = Fuller C
| author affiliation = PUBLIC SERVICE CO. OF COLORADO
| author affiliation = PUBLIC SERVICE CO. OF COLORADO

Latest revision as of 21:04, 23 May 2020

Issue 55 to Abnormal Operating Procedure AOP-R, Loss of Access to Control Room
ML20070V687
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 03/20/1991
From: Fuller C
PUBLIC SERVICE CO. OF COLORADO
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
AOP-R-I55, P-91114, NUDOCS 9104120059
Download: ML20070V687 (5)


Text

..

. O. Pubile Sery co' gglc-Denver, co 8020b eMO 16805 WCR 19 1/2, Platteville, Colorado 80551

., April 5, 1991 Fort St. Vrain

{

Unit No. 1 P-91114 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop P1-37 Washi'igton, D.C. 20555 DOCKET NO: 50-267

SUBJECT:

PROCEDURE DISTRIBUTION ,

i Gentlemen: _.

We are transmitting herein the following -

Issue 55 of Abnormal Operating Procedure R 4

Two copies of this procedure have also been transmitted to Region IV.

Emergency Response Coordinator, in accordance with 200FR50.54(q)

(ReferenceP-91115).

In accordance with 10CFR50.54(q), we have determined.that the changes in this issue do not. decrease the effectiveness of.the Fort St. Vrain Emergency Plans and the plans, as changed,. continue to meet the ,

intent of 10CFR50.47(b) and 10CFR50 Appendix E. '!

If difficulties or questions arise in filing this procedure, please contactMr.M,H.Holmesat(303)480-6960.

Sincerely.

. Charles H. Fuller Manager, Nuclear Production Fort St. Vrain Nuclear 1 Generating Station I CHF/bj Attachments cc: J. B. Baird Senior Resident Inspector Fort St. Vrain

- Renee Millison /

tanine Fmeroency Planning Specialist 90133 2 TsR"ngggg0;ggCqg6, P Pf0R

.p';-)i

- Page 2 of 2 FORT ST. VRAIN NUCLEAR GENERATING STATION O Public Service

  • Puntic senvice company or cotonApo 03/20/91

,. . ABNORMAL OPERATING PROCEDURES ISSVE EFFECTIVE NO. SUBJECT NUMBER DATE J DELETED 05-14 82 AOP-K-1 Environmantal 01sturbances - Earthquake 59 04-19-90 AOP-K-2 Environmental Disturbances - Tornado 56 04-19-90 AOP L Loss of an Instrument Air Header 57 04 19-90 AOP-EP M Loss of Hydraulic Power 56-Last 03-21-90

. c AOP-N Loss of an Instrument Bus 56 04-19-90 AOP-P Loss of a 0.C. Bus 57 04-19-90 AOP-EP Q $ team Leak or inadvertent Lifting of Steam Relief Valve 57-Last 04-25-90 l A0P-EP R Loss of Access to Control I Room 55 03-20-91 A0P-EP S Loss of HVAC to 480 Volt Switchgear Room 54-Last 03-28-90 AOP-V Restoration of PCRV Integrity 1 11-05-90 EP CLASS Event and Emergency Classification Overview 7 07-26-89 l

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  • Page 1 of 2
  • j Pub llC FORT ST, VRAIN NUCLEAR GENERATING STATION , "h

$4fYlCO' Pusuc sanv6cs COMPANY OF COLORADO 03/20/91 '

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  • 1 i

.. . ABNORMAL OPERATING PPOCEDURES

!$$UE EFFECT!VE NO. $UBJECT NUMBER DATE AOP INTRO Abnormal Operating Procedures Introduction t6 02-13 91 AOP-A Moisture In-Leakage 58 02-13 91 AOP B Reactor $ cram $8 02-13-91 1

EP B-2 DELETED 01-09-88 AOP EP c Loop Shutdown 57-Last 03-28-90 , ,

A0D 0-1 Single Circulator Trip $6 02-13-91 A0P-EP 0 2 Three Circulator Trips 54 Last 03-21-90 AOP-EP E Abnomal Reactor Power Change $6-Last 03-28-90 O AOP F Restoration of Essential Electric Power 1 11-05 90 AOP F,p F 1 Main Turbine Emergencies 58-Last 03-28-90 '

AOP-EP F-2 Low Condenser Vacuum Turbine Trip 55-Last 03-28-90 AOP-EP F-3 Loss of Outside Power and Turbine Trip 55-Last 03-28 90 A0P-EP F-4 Loss of Outside Power and Turbine Trip with Failure of One Diesel l Generator $et to Start 55-Last 03-28-90 AOP-EP G Loss of Active Core Cooling 56-Last 03-28 90 AOP-H-1 Abnormal Radioactive Liquid Waste From Plant 57 04-19-90 l AOP-H-2 Abnormal Radioactive Gas Release From Plant 57 04-25-90 AOP-H-3 High Activity in the Plant 57 04-19-90 AOP-! Discussion of Fire - 56 08-01-90 l AOP-I-2 Chemical Spill Response 1 01-16-91 FORM (Ol372 22 3M3 - - -

4

.; , 1 AOP-R i Issue 55 v l

., Public FORT ST. VRAIN NUCLEAR GENERATING STATION \\ l

, $9fVlC9' Pustic SERVICE COMPANY OF COLORADO I l

TITLE: LOSS OF ACCESS TO CONTROL ROOM RESPONSIBLE R

. [ LT,$/k ,8Y: AUTHORIZED FOR: 7 _

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AUTH(RIZED BY' Ia W 'cwE nj@w PCfC 9 2TM 131991 $7Te g,bq i DCCF NUMBER (S) kh \2LJ-h 4

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FORM (E)372 22 3042

- - . - , - ~ . . _ , _ . , _ . _ . . - . . _ , . . . _ . - - . . . _ . - _ , _ . . . - . . . - _ _ _ __

. l AOP-R Issue 55 Page 2 of 2 4

8 Public FORT ST. VRAIN NUCLEAR GENERATING STATION l  %)7 Service

  • Pusuc senvece comeAuv or cotonAno O (R)

LOSS OF ACCESS TO CONTROL ROOM t

SYMPTOM-ACTION MATRIX l ~

l l l l l l l SYMPTOM l I l ~~~ I l l l l 1.1 l l l ACTIONS l Loss of Access. l l l l0f Control Room l l l l l 1 l l OPERATOR ACTION l l l 2.1 l l l Evacuate to I-49 and XX XX l l l terminate Defueling l l l activities.

l I .

l l l l 1 2.2 l l l Monitor the start up channel l XX XX l l l recorder at I-49 (alternately l l l l monitor the log nuclear powerl l l l Indication at I-49) to ensure.: l l l reactor is shutdown.

l l 2.3 l XX XX- l l l Utilize OPOP III.D to l l l l maintain liner cooling. l l I I l l

l O l l

- FORM (01372 22 3643 l

__ ~. . ._. _ _ _ . . - _ , . - , , , - . _ , . _ _ _ . . _ . _ , . . _ . , . . . _ _

1 AOP APP R Issue 55

'9'

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  • hPublic FORT ST. VRAIN NUCLEAR GENERATING STATION pusuc sanvece comeAwy or cotonaoo NGF Service *'

INTRODUCTION l In the event that immediate Control Room evacuation is necessary, the l Plant can still be monitored from a redundant control panel in the l 480V switchgear room and local indication in the plant.

DISCUSSION OF SYMPTOMS I SYMPTOMS l 1.1 Loss of Access to Of Control Room l If Control Room evacuation is required and defueling i activities have not been terminated from the Control Room, notify Fuel Deck from I-49 Panel Area.

Control Room access may be lost due to fire, smoke, structural damage, intruders, radiation, toxic fumes, or any other reason, but should be very apparent. ,

O!$CUSSION OF OPERATOR ACTION OPERATOR ACTION O l 2.1 Evacuate to I-49 and Terminate Oefueling Activities

)

l When Control Room evacuation is required:  !

1) Evacuate to I-49 in the-480V Swftchgear Room.

l Terminate defueling activities and ensure all PCRV l openings closed, j 2.2 Monitor the Startup Channel Recorder at I-49 l Ensure that reactor is shutdown by monitoring the startup I channel recorder nn I-49. If startup channel recorder is l not available then. monitor the log nuclear power l indication on I-49.

l 2.3 Utilize OPOP 111.0 to Maintain Liner Coolina l OPOP 111.0 provides methods for liner cooling.

O FoRMtol372 22 36(I

!