ML20034C091
| ML20034C091 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 04/27/1990 |
| From: | Fuller C PUBLIC SERVICE CO. OF COLORADO |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20034C092 | List: |
| References | |
| P-90137, NUDOCS 9005020056 | |
| Download: ML20034C091 (111) | |
Text
,
O Public Service' O*"A-.
P.o. Box 840 oenver, Co 00201 0840 l
16805 WCR 19 1/2, Platteville, Colorado 80651 l
l_
Ahril27,1990 i
Fort St. Vrain Unit No. 1 P-90137 1
U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop PI-37 Washington, D.C.
20555 DOCKET NO:
50-267
SUBJECT:
ABNORMAL OPERATING AND EMERGENCY OPERATING PROCEDURE DISTRIBUTION Gentlemen:
i We are transmitting herein the following:
Issue 55 of AOP-INTRO Issue 59 of A0P-K-1 Issue 57 of A0P-A Issue 56 of A0P-K-2 Issue 57 of AOP-B Issue 57 of AOP-L' Issue 55 of AOP-D-1 Issue 56 of AOP-N Issue 57 of A0P-H-1 Issue 57 of A0P-P Issue 57 of AOP-H-2 Issue 57 Last of AOP-EP Q Issue 57 of AOP-H-3 Issue 3 of E0P-1 Two copies of these procedures have also been transmitted to Region IV, Emergency Response Coordinator, in accordance with 10CFR50.54(q)
(Reference P-90138).
In accordance with 10CFR50.54(q), we have determined that the changes in these issues 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.
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9005020056 900427
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PDR ADOCK 05000267 P
PDC L
3
~P-90137 Page 2 April 27,.1990 1
If difficulties or questions arise in filing these procedures, please.:
.contactP,r.M.H.Holmesat(303)480-6960.
Sincerely, llu.
Charles H. Fuller-
~Manageri Nuclear Production s.
Fort St. Vrain Nuclear
- enerating. Station G
~
.CHF/jgr Attachments.
cc:
Robert Farrell
. Senior Resident: Inspector-Fort St. Vrain Renee Millison Senior Emergency Planning-Specialist Fort St. Vrain s
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Page 1 of 2' cj APublic FORT ST. VRAIN NUCLEAR CENERATING STATION
%F Service
- Pusue sanvice compasov or cotonAoo 04/19/90
-g O
ABNORMAL OPERATING PROCEDURES ISSUE EFFECTIVE NO.
SUBJECT NUMBER DATE l INTRO Abnormal Operating Procedures l
Introduction 55 04-19-90 lA Moisture In-Leakage 57 04-19-90 iB Reactor Scram 57 04-19-90 B-2 DELETED 01-09-88 C
Loop Shutdown 57 w. 03-28-90 l D-1 Single Circulator Trip 55 04-19-90
.D-2 Three Circulator Trips 54-Last 03-21-90 E
Abnormal Reactor Power Change 56-Last 03-28-90 F-1 Main Turbine Emergencies 58-Last 03-28-90 F-2 Low Condenser Vacuum Turbine Trip 55-Last 03-28-90 F-3 Loss of Outside Power and Turbine
' Trip 55-Last 03-28-90 l
F-4 Loss of Outside Power and Turbine Trip with Failure of One Diesel Generator Set to Start 55-Last 03-28-90 i
G Loss of Active Core Cooling 56-Last 03-28-90 l H-1 Abnormal Radioactive Liquid Waste l
From Plant 57 04-19-90 H-2 Abnormal Rad;oactive Ga* Release From Plant' 56 06-30-89 l H-3 High Activity in the Plant 57 04-19-90 I
Discussion of Fire 55 06-30-89 J
DELETED 05-14-82 l K-1 Environmental Disturbances - Earthquake 59 04-19-90 l K-2 Environmental Disturbances - Tornado 56 04-19-90 FORM 101372 22 3643 l
,[f
,f Page 2 of 2 l
A Public FORT ST. VRAIN NUCLEAR CENERATING STATION f
j YW Service
- Pusuc senvecs comeAmy or cotonApo 04/19/90 u
O ABNORMAL OPERATING PROCEDURES l
i ISSUE EFFECTIVE NO.
SUBJECT NUMBER DATE i
i l
lL Loss of an Instrument Air l
Hender 57 04-19-90
(
M Loss of Hydraulic Power 56-Last 03-21-90 l
lN Loss of an Instrument Bus 56 04-19-90 l
lP Loss of a D.C. Bus 57 04-19-90 Q
Steam Leak or Inadvertent Lifting of Steam Relief Valve 56 06-30-89
{
R Loss of Access to Control Room 54 06-30-89 S
Loss of HVAC to 480' Volt Switchgear Room 54-Last 03-28-90 l
~
CLASS Event and Emergency Classification Overview 7
07-26-89 i
9 I
b b
t' O
8 FORMiD)372 22 "Je43 t
3 m
.-r s
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m
l Page 1 of 2 Pubil3 FORT ST. VRAIN NUCLEAR GENERATING STATION
$9fVlCO*-
PUBUC SERVICE COMPANY OF COLORADO 04/25/90 ABNORMAL OPERATING PROCEDURES ISSUE EFFECTIVE NO.
SUBJECT NUMBER DATE INTRO Abnormal Operating Procedures Introduction 55 04-19-90 A
Moisture In-Leakage 57 04-19-90 B
Reactor Scram 57 04-19-90 B-2 DELETED 01-09-88 C
Loop Shutdown 57-Last 03-28-90 D-1 Single Circulator Trip 55 04-19-90 D-2 Three Circulator Trips 54-Last 03-21-90 E
Abnormal Reactor Power Changs 56-Last 03-28-90 F-1 Main Turbine Emergencies 58-Last 03-28-90 F-2 Low Condenser Vacuum Turbine Trip 55-Last 03-28-90 F-3 Loss of Outside Power and Turbine Trip 55-Last 03-28-90 F-4 Loss of Outside Power and Turbine Trip with Failure of One Diesel Generator Set to Start 55-Last 03-28-90
- j G
Loss of Active Core Cooling 56-Last 03-28-90 H-1 Abnormal Radioactive Liquid Waste From Plant 57 04-19-90 l H-2 Abnormal Radioactive Gas Release 1
From Plant 57 04-25-90' H-3 High Activity in the Plant 57 04-19-90 I
Discussion of Fire 55 06-30-89 J
DELETED
'05-14-82 K-1 Environmental Disturbances - Earthquake 59 04-19-90 K-2 Environmental Disturbances - Tornado 56 04-19-90 l
FORM (D)372 22 3643 J
Page 2 of 2
@Pubils FORT CT. VRAIN NUCLEAR CENERATING STATION Service *
- Pusue SERVICE COMPANY OF COLORADO M/25/90 ABNORMAL OPERATING PROCEDURES ISSUE EFFECTIVE NO.
SUBJECT NUMBER DATE L
Loss of an Instrument Air Header 57 04-19-90 M
Loss of Hydraulic' Power Last.03-21-90 N
Loss of an Instrument Bus 56 04-19-90 P
Loss of a D.C. Bus 57 04-19-90 l0 Steam Leak or Inadvertent l
Lifting of Steam Relief Valve 57-Last.04-25-90 R
Loss of Access to Control Room 54 06-30-89 S
Loss of HVAC to 480 Volt Switchgear Room Last 03-28-90 CLASS Event and Emergency Classification i
Overview 7
07-26-89 t
FORM (D)372 22 3643
-f l.
.7
'AOP INTRO
~
Issue 5b PORT ST.-VRAIN NUCLEAR CENERATIN3 STATION age 1 of 5
\\j ePublic P
SerVICO' PU8uc 88RV908 CORAPANY OF COLORADO O
l TITLE:
ABNORMAL OPERATING PROCEDURES INTRODUCTION d / A NuiN2c AUTHO(lZED T ','
9Y w i a= w
<t n
((EW 8II 1
4-Vl-40 re, e
- l9 NUMBER (S) hO" M i
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808 C P ggs O
FORMtD1372 22 3842
l AOP INTRO e
Issue 55 A Public FORT ST. VRAIN NUCLEAR GENERATING STATION "I' W Service
- PusuC saRVICE COMPANY OF COLORADO (v3 I.
FUNCTION:
l The Abnormal Operating Procedures provide instructions for the operating staff to return systems and equipment to normal l
following the use of the Emergency Operating Procedures.
l Each Abnormal Operating Procedure provides the operator with the symptoms needed to determine that an abnormal condition does exist and the operator actions which he must perform to prevent further deterioration of plant parameters or to return the plant to normal. It is no longer necessary that the symptoms and immediate actions be committed to memory.
Immediate actions are now included in the-Emergency Operating Procedure (EOP) set.
l Each Abnormal Operating Procedure also includes the actions required to return the plant to a more normal condition and/or to cope with further slowly developing deterieration of plant parameters. The actions also contain steps requiring more complex reasoning or analysis.
l The Abnormal Operating Procedure are an integral part of the overall FSV emergency preparedness program. The Abnormal l
Operating Procedure have been structured su as to facilitate the l
transition from Abnormal Operating Procedure to the appropriate q
RERP implementing procedure or event reporting procedure with Q
minimal delay or confusion.
In order to further aid with classification and reporting decision making, an " Event and Emergency Classification Overview" procedure is provided at the back of this document. This procedure discusses the classification systems, provides guidelines for event classification, serves as a reference for pertinent reporting or activation tables, and provides a summary table that discusses reporting / activation requirements for af symptoms presented in j
these Abnormal Operating Procedure, i
l l
The Abnormal Operating Procedure are intentionally brief to be suitable for implementation. To provide the background and I_
explanation required for study and understanding of the.
procedures by the operators, separate appendices have been prepared. The appendices are indexed and titled to correspond I
to the Abnormal Operating Procedure they support. It should be emphasized, however, that the appendices are study guides only and are neither needed, nor intended, for use during abnormal plant conditions.
l O
L FORMIDl372 22 3643 t
.y.
l AOP INTRO Issue 55 Public FORT ST. VRAIN NUCLEAR GENERATING STATION '9'
+
$6fVlC9" PUBUC SERVICE COMPANY OF COLORADO II. FORMAT:
1 Each Abnormal Operating Procedure is presented in a. symptom -
action matrix format consisting of symptoms, and operator actions. Symptoms include plant conditions, alarms, and indications that are associated with the condition. The operator actions are few, and as brief as possible to stop the degradation of conditions, mitigate their consequences, and allow the operators time to evaluate the situation.
The symptom - action matrix presentation format was selected for a number of reasons, as nilows:
l A.
It provides an abbreviated presentation of symptoms and operator actions which must be readily usable during an abnormal plant condition, i
B.
It allows specific operator actions to be identified against specific alarms or plant conditions; and, i
C.
It does not preclude the use of precautionary notes or caution statements where deemed appropriate.
O-An additional feature of the symptom-action Matrix format is that it permits east end (turbine) and west end (reactor) operator actions to be identified as follows:
West S.S. East I
l lxx xx xxl l
1 1
When an action statement includes multiple steps involving both east end and west end operator actions, both sides of the block are marked. When an action statement pertains to only the east or west end operator action (s), only that portion of the block is marked. This presentation format does not preclude, for example, an east end operator performing a west end action when appropriate during an abnormal condition. Actions or decisions to be performed by the Shift Supervisor are marked in the center of the block.
l III. ADMINISTRATIVE RULES:
A.
It shall be the responsibility of the Shift Supervisor or I
the reactor operator to terminate defueling activities down when the safety of the reactor is in jeopardy or a reactor protection circuit setpoint has been exceeded.
O FORM tDl372 22 3643.
l AOP INTRO e
Issue 55 i
page 4 of 5 i
APublic FORT ST. VRAIN NUCLEAR GENERATING STATION j
%F Service
- PUBUC 88RV6CE COMPANY OF COLORADO O
'B.
It shall be.the responsibility of the Shift Supervisor to l
investigate an unexplained count rat.e change and report his i'indings to the Station Manager or Superintendent of l
Operations.
C.
It shall be the responsibility of all employees to gain a working knowledge of the Technical Specifications as they apply to specific joh requirements, and to take appropriate steps to assure compliance with them.
IV. ALARMS AND NOTIFICATION OF EMERGENCIES:
A.
The_ audible alarm system in the control room, referred to in the procedure as an " alarm" or " common alarm", is an automatically actuated annunciator system with three distinct alarm sounds. They are:
(1)
A " Siren" indicating reactor scramt (2)
A " Bell" indicating loop shutdown, circulator trip;-
- and, (3)
A " Horn" indicating any equipment system abnormalities, and I-09 alarm.
As required, the control room annunciator alerts the operating staff to an abnormal condition in the plant.
The reactor operator has control over the duration and
'1 silencing of all alarms.
B.
The plant emergency alarm consists of two distinct sounds.
These sounds will be broadcast over the plant Gai-Tronics system to warn personnel of an emergency in the plant.
The two alarms are:
(1)
Siren general alarm to' indicate fire or other emergency.
(2)
Yelping - radiation alarm.
The plant emergency alarm is activated by operating personnel in the control room. All personnel, upon hearing the alarm, shall report immediately to their I
pre-assigned emergency station for accountability and further instructions as designated in Administrative Procedure G-5, " Personnel Emergency Response". Visitors shall be escorted to the security building for signout and exit from the plant.
The Shift Supervisor shall, as soon as possible, announce over the Gai-Tronics system, the nature of the emergency, O
and any pertinent instructions to the plant personnel.
FORM (o)372 22 3643 J
l AOP INTRO a
Issue 55.
"9' U
APublic FORT ST. VRAIN NUCLEAR GENERATING STATION 107 Service
- Pusuc sanve.s COMPANY OF COLORADO V.
COMMUNICATIONS:
During an emergency situation requiring removal of plant personnel from the plant to either an-onsite or offsite location, communication lines shall be established as described in the Radiological Emergency Response Plan.
VI. SUPPORT PERSONNEL:
In the event that any emergency condition exists which requires notification of plant management, the Shift Supervisor, or his designee, shall notify a member of plant management (denoted in the Control Room implementing procedure), who shall be responsible for the notification of the remaining plant managtment personnel and department supervisors.
VII. COMMITMENTS:
1 None V
FORM (D)T72 *2 3643
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