ML20134E365
| ML20134E365 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 08/06/1985 |
| From: | Gahm J PUBLIC SERVICE CO. OF COLORADO |
| To: | Johnson E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| P-850277, PROC-850806, NUDOCS 8508200174 | |
| Download: ML20134E365 (11) | |
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Public FORT ST. VRAIN NUCLEAR GENERATING STATION SerVICO PUBLIC SERVICE COMPANY OF COLORADO 7/19/85 l
O FMERGENCY PROCEDURES ISSUE EFFECTIVE NO.
SUBJECT NUMBER DATE 50 05-14-82 Intro A
Moisture In-Leakage 52 08-14-84 B-1 Reactor Scram (Without Two Loop Trouble) 52 08-14-84 B-2 Two Loop Trouble Scram, With a Trouble Alarm in Operating Loop 51 08-14-84 C
Loop Shutdown 51 08-14-84 D-1 Single Circulator Trip or One Circulator Trip in Each Loop 52 06-27-85 D-2 Three Circulator Trips 51 08-14-84 lE Abnormal Reactor Power Change 52 07-19-85 F-1 Main Turbine 52 08-14-84 F-2 Low Condensor Vacuum Turbine Trip 52 08-14-84 F-3 Loss of Outside Power and Turbine 52 06-27-85 Trip F-4 Loss of Outside Power and Turbine Trip with Failure of One Diesel Generator Set to Start 51 08-14-84 G
Extended Loss of Active Core Cooling 51 08-14-84 H-1 Abnormal Radioactive Liquid Release From Plant 51 08-14-84 H-2 Abnormal Radioactive Gas Release From Plant 51 08-14-84 H-3 High Activity in the Plant 51 08-14-84 I
Fire 52 08-14-84 05-14-82 J
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O K-1 Environmental Disturbances - Earthquake 53 06-27-85
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K-2 Environmental Disturbances - Tornado 51 08-14-84 y$
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4 Page 2 of 2 OSerVICe Public FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE COMPANY OF COLORADO OG EMERGENCY PROCEDURES ISSUE EFFECTIVE N0.
SUBJECT NUMBER DATE L
Loss of an Instrument. Air Header 52 01-18-85 M
Loss of Hydraulic Power 51 08-14-84 N
Loss of an Instrument Bus 52 08-14-84 P
Loss of a D.C. Bus 51 08-14-84 Q
Steam Leak on Inadvertent Lifting of a Steam Relief Valve 50 05-14-82 R
Loss of Access to Control Room 51 08-14-84 S
Loss of HVAC to 480 Volt O
Switchgear Room 51 08-14-84 CLASS Event and Emergency Classification Overview 3
06-27-85 O
FORM (C)372 22 3643
EP E Issue 52 Public FORT ST. VRAIN NUCLEAR GENERATING STsTION Page 1 of 3 O SerVICO PUBLIC SERVICE COMPANY OF COLORADO{ }*mmm>m.,
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ABNORMAL REACTOR PtMER CllANCE
,',"""') og 3 SYMPTOH-ACTION MATRIX SYHFiltr*.
ACTIONS 3.1 1.2 1.3 1.4 Reactivity Change Renetivity 4:hnnge Re-Slurk t'able Any Unexplained within Compensating yond'Compenanting JHJA. 4-3 Reactivity Change Ability of Reg. Rod Ahllity of Reg. Hml.
Deemed Unsafe by REPORT 1NC/ ACTIVATION 4.1 The event carries no reporting / activation requirements beyond what the Shift Supervisor XX deems appropriate.
4.2 The event, as written, is reportable as a "Non-Emergency Event." A Dre-Ilour Report is required if shutdown is required per Technten1 Specifica-XX XX tions. A Four-Hour Report is required if a scram is manually performed or if it occurs due to PPS action, or if the event is one which could have prevented the reactor from being placed in a safe shutdown condition (see Table 1.1-1. Item 3).
4.3 The event, as written, is reportable as a "Non-Emergency Event." to be reported as in 4.2 above, provided the alarm is authentic. and requires XX s scram. The event would escalate to a SITE AREA r3ERCENCT if there was an inability to insert sufficient rods to unintain adenuate shutdown i margin, and a failure of the Reserve Shutdown System to crerate adequately to maintain a e
.Olap shutdown m.1rgin.
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EP APP E Issue 52 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 1 of 5 O Service ~pusuC SERVICE COMPANY OF COLORADO
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INTRODUCTION Sudden changes in the reactivity status of the core which cannot be accounted for by control system or operator actions may be
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indications of potentially serious problems. Any such indications should receive immediate operator attention and should be fully investigated. The only credible source of significant changes in reactivity is the removal or insertion of control poisons.
In this event, the operator may not have sufficient control to safely maintain the reactor at power. Thus, an immediate scram and shutdown of the power plant are appropriate.
The possible causes of the unintentional removal or insertion of control poisons are:
1)
Withdrawal of one or more rods due to switching malfunction.
2)
Control rod stuck:
a)
Rod binding in channel due to a shift in the core or a ruptured or deformed absorber; b)
Jammed drive mechanism; c)
Failure of-brake to release or brake hangup; d)
Faulty indicating devices; or, s s s
e)
Drive motor breaker trip or control system fuse blown.
Since a stuck rod could indicate a serious condition, such as a deformed or ruptured absorber, or a shift of the core, which might affect other rods similarly, continued operation may aggravate the situation.
l With one or more rod pairs inoperable due to being l
immovable (i.e., not capable of being fully inserted) as a l
result of excessive friction or mechanical interference, l
immediately initiate a reactor shutdown and be in at least l
SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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FORM {C)372 22-3643
I EP APP E Issue 52 OService" Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 2 of 5 PUBLIC SERVICE COMPANY OF COLORADO v
3)
Control rod drop:
a)
Broken suspension cable or spine; b)
Brake failure (probably electrical trouble); or, c)
Electrical failure of motor.
A dropped rod causes changes in the core power distribution.
If the core power demand, as determined by turbine generator load, remains unchanged and compensation is accomplished by withdrawing other rods, Technical Specification limits on inserted rods may be violated, and higher than normal temperatures may occur in some regions.
In addition, the remaining rod or portions of the rod pairs, may not be depended on to scram because of the possibility of cable entanglement.
4)
Insertion of a small amount of reserve shutdown poison:
If insertion of reserve shutdown poison occurred, and an attempt was made to compensate for it by withdrawal of control rods, a power tilt most certainly would exist, which would result in high fuel temperatures in some regions.
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DISCUSSION OF SYMPTOMS 1.1 Reactivity change within compensating ability of regulating rod.
1.2 Reactivity change beyond compensating ability of rsgulating rod.
Unexplained reactivity change causing changes in reactor prwer level is a prime indicator that events are occurring without the operators knowledge and/or beyond his control.
This situation requires immediate investigation and/or action dependent upon the magnitude of the reactivity change.
l If the unexplained reactivity change is within the l
compensating ability of the regulating rod, an orderly l
investigation and corrective action as appropriate should l
be performed without delay.
If the unexplained reactivity change is beyond the l
compensating ability of the regulating rod, a significant change in reactivity has occurred and an immediate reactor l
manual scram is appropriate.
O) c FORM (C)372 22 3643
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EP APP E Issue 52 O 59IViC9" Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 3 of 5 PUBLIC SERVICE COMPANY OF COLORADO 1.3 Slack cable I-03A, 4-3.
The slack cable alarm system's purpose is to detect a stuck rod situation which, in turn, could be the source of an abnormal reactivity change.
1.4 Any unexplained reactivity change deemed unsafe by operator.
This gives the operator license to scram the reactor any time he considers it necessary.
This is done in recognition of the fact that written procedures cannot anticipate all possible problems and combinations of circumstances that might render further operation unsafe.
The operator's judgement,
- training, knowledge, and experience form an important part of the overall safeguards system protecting the health and safety of the public.
DISCUSSION OF IMMEDIATE ACTION 2.1 Scram reactor per Emeroency Procedure B-1.
This is the appropriate action when the reactivity change p/
is greater than the regulating rod worth, or when the t
operator deems the situation unsafe.
DISCUSSION OF FOLLOWUP ACTION 3.1 Check for moisture ingress.
3.2 Check for abnormal control rod position indications.
3.3 Check for reserve shutdown system or hopper actuation.
These are the most probable causes of reactivity change and can be quickly checked out.
If the reactor is scrammed, the control rod position indicators should be monitored during the scram.
If a questionable rod pair is identified and no slack cable alarm has sounded, its status can be determined while operating at power per the following steps:
1)
Select affected rod pair drive with the individual rod select switches.
2)
Record rod pair position (Digital and Analog).
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f FoRMICl372 22 3643
EP APP E Issue 52 O SerVIC9" Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 4 of 5 PUBLIC SERVICE COMPANY OF COLORADO p)
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With the individual rod actuate switch, jog the rod in, in increments of one-half (1/2) inch or equivalent time for a maximum of three (3) inches.
4)
Determine status of rod pair by observing position indicators, rod limit lights, slack cable alarm,
- and, finally, reactivity change which backs up the direct rod positioning instrumentation.
3.4 Perform slack cable check per SOP 12-01, Section 5.2.
When the slack cable alarm has sounded, the status of the questionable rod pair is determined using the 50P.
3.5 Perform orderly shutdown if required.
When the situation warrants, or as required by the Technical Specification limits, an orderly
- shutdown, rather than a scram, should be implemented. Control indications must continue to be monitored and appropriate action, including scram instituted, if necessary.
3.6 If required, actuate reserve shutdown system.
This action should be taken if the control rods are unable f\\
to effectively shut down the reactor or if the shutdown d
margin with rods fully inserted is not considered adequate. Because of the additional work required to remove the reserve shutdown material from the core, this action should not be taken lightly. However, if there is any doubt in the operator's mind about the ability of the control rod system to shutdown the reactor and maintain an adequate shutdown margin, it is appropriate to activate the reserve shutdown system.
REPORTING / ACTIVATION 4.1 The event carries no reporting / activation requirements beyond what the Shift Supervisor deems appropriate.
The event, as written, carries no immediate reporting requirements, unless the reactivity anomaly is of the I
nature described in Item 3.F on Table 1.3-1 of EP-CLASS.
4.2 The event, as written, is reportable as a "Non-Emergency Event".
The
- event, if a result of necessitating manual or automatic scram, is reportable as a "Non-Emergency Event,"
and should be reported to the NRC within one hour if required per Technical Specifications, or within four O
hours otherwise, in accordance with RERP-CR.
V FORM (C)372 22 3643
EP APP E Issue 52 OServlCe*
Public FORT ST. VRA!N NUCLEAR GENERATING STAT!ON Page 5 of 5 PUBUC SERVICE COMPANY OF COLORADO AU 4.3 The event, as written, is reportable as a "Non-Emergency Event," provided the alarm is authentic, and requires a scram.
The event would escalate to a SITE AREA EMERGENCY
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if there was an inability to insert sufficient rods to maintain shutdown margin and a failure of the reserve shutdown system to operate adequately to maintain a
.Olap shutdown margin.
Verify that the slack cable alarm is aut%.c.ic; if it is, this event would be reportable as a "Non-Emergency Event" as described in 4.1, in accordance with RERP-CR.
If the event results in an inability to maintain a.01Ap shutdown margin at 220 F, then the event should be classified a SITE AREA EMERGENCY, and the RERP should be implemented according to RERP implementing procedure RERP-CR.
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FORMICl372 22 3543
O eubiicservice
=::= =.-
16805 WCR 19 1/2, Platteville, Colorado 80651 August 6, 1985 Fort St. Vrain Unit No. 1 P-85277 RDW l
Regional Administrator i
i u ear Regulatory Commission Als 1525 611 Ryan Plaza Drive, Suite 1000 d'l Arlington, TX 76011
__J ATTN: Mr. E. H. Johnson Docket No. 50-267
SUBJECT:
Emergency Procedures
Dear Mr. Johnson:
We are transmitting herein revisions to Fort St. Vrain's Station Emergency Procedures for Mr. Phil Wagner's copy of the Emergency Procedures.
One copy of the Emergency Procedure, E, Issue 52 is being transmitted d
for filing. Attachments, data sheets, checklists, and control lists should immediately follow the procedure.
If difficulties or questions arise in filing this procedure, please contact Mr. M. H. Holmes at (303) 571-8409.
Sincerely, J. W. Gahm Manager, Nuclear Production i
JWG/dal Attachments
@ea 92-139
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