ML20066J117

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Issue 56 to Intro Section of Abnormal Operating Procedure (Aop),Issue 58 of AOP-A,Issue 58 to AOP-B,Issue 56 of AOP D-1 & Issue 2 of RERP-TRANSPORTATION
ML20066J117
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 02/15/1991
From: Deniston M, Fuller C
PUBLIC SERVICE CO. OF COLORADO
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
P-91070, PROC-910215, NUDOCS 9102250251
Download: ML20066J117 (36)
v • d • e


Text

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O Pubhc Service

.Public Service' c-P.o, Box B40 ce--

Denver, to 00201. OMO 16805 WCR 19 1/2, Platteville, Colorado 80651 February 15, 1991 Fort St. Vrain Unit No. 1 P-91070 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop P1-37 Washington, D.C. 20555 DOCKET NO: 50-267

SUBJECT:

PROCEDURE DISTRIBUTION Gentlemen:

We are transmitting herein the following:

Issue 56 of AOP INTRO 15' sue 58 of AOP-A Issue 58 of AOP-B Issue 56 of A0P D-1 Issue 2 of RERP-TRANSPORTATION Two copies of these procedures have also been transmitted to Region IV,-Emergency Response Coordinator, in accordance with 10CFR50.54(q)

(ReferenceP-91072),

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, f i' i

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e P-91070 Page 2 February 15, 1991 if difficulties or questions arise in filing-these procedures, please '

contact Mr. M. H. Holmes at (303) 480-6960.

Sincerely, h

Charles H. Fuller Manager, Nuclear Production Fort St. Vrain Nuclear Generating Station CHF/bj Attachments' cc: J. B. Baird Senior Resident Inspector Fort St. Vrain Renee Millison Senior Emergency Planning Specialist Fort St. Vrain

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.;9 Lg w/ 1-ABNORMAL OPERATING PROCEDURES ISSUE EFFECTIVE' d NO. SUBJECT NUMBER DATE TINTRO- Abn.ormal Operating Procedures ll Introduction- 56 02-13-91

-lLA Moisture In-Leakage 58 02-13-91 1B _ Reactor Scram 1 58 02-13-91 i B-2 0ELETED. 01-09-8B R

-C' -Loop Shutdown- 57-Last 03-28-90 i;: 0-l' Single Circulator Trip 56 02-13-91 0-2 :Three= Circulator Trips. Last 03-21-90

\ E1 Abnormal Reactor Power Change. 56-Last 03-28-90 F~

--Restoration of Essential Electric Power 1 11-05-90

' F-li

~ Main' Turbine Emergencies 58-Last 03-28-90 cF -

" LbwlCoridenser . Vacuum Tubbine Trip 55-Last 03-28-90.-

--F-3 lloss of Outside' Power and Turbine Trip 55-Last 03-23-90i F-4s

' Loss of1Outside Power 'and Terbine-

. Trip.with Failure of.-One Diesel-

~

, Generator Set to Start:- 55-Last 03-28-90

Gi ' Loss -of: Activ'e Core Cooling .56-Last 03-23 l }i-1 t
Abnormal: Radioactive Liquid Waste From Plant' 57 04-19-90 in -

m H-2.

'  : Abnormal Radioactive. Gas Release From Plant- 57 04-25-90

- H_-3 High Activity in the Plant 57 4

04-19-90 I' Discussion of Fire

, 56 08-01-90

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_1- 2 Chemical Spill Response h ' 1 01-16-91 FORM 01372 22 3843 kJ , - , ,.,_, , _ _ . _ . . . . . ._. _ . . _ _ . .

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FORT ST. VRAIN NUCLEAR GENERATING STATION 02/13/91 1

OPublicSGIVlCO' PUBUC SERVICE COMPANY OF COLORADO R

ABNORMAL OPERATING PROCEDURES ISSUE EFFECTIVE SUBJECT NUMBER DATE NO.

05-14-82 ,

J . DELETED Environmental Disturbances - Earthquake 59 04-19-90 K-1 Environmental Disturbances - Tornado 56 04-19-90 K-2 L Loss of an Instrument Air Header 57 04-19 M Loss of Hydraulic Power 56-Last 03-21-90 Lo:s of an lastrument Bus 56 04-19-90 N

Loss of 1 0.C.. Bus 57 04-19-90 P

Q Steam Leak or inadvertent 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 54-last 03-23-90 Restoration of PCRV Integrity 1 11-05-90 V

. CLASS Event and Emergency Classification Overview 7 07-26-89 n

9

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AOP INTRO o- Issue 56 Public FORT ST, VRAIN NUCLEAR GENERATING STATION Page 1 of 5 9 '/ '{

) SOfVIC'O' PusuC SERVICE COMPANY OF COLORADO xs ilTLE: ABNORMAL OPERATING PROCEDURES INTRODUCTION RESPONSIBLE A AUTHORIZED FOR: e b).( NOx[k m~ .BY: '

AUTHOR BY: Q \F' a h.s  % _

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Public FORT ST VRAIN NUCLEAR GENERATING STATION i, Serv lde* PusuC SERVICE COMPANY OF COLORADO yy "a ,

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I; FUNCTION:-

-The Abnormal-Operating Procedures provide instructions for the -

-. operating staff to return systems and equipment to normal

-following the use of the Emergency Operating Procedures.

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 patameters or to return the plant to normal.

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 deterioration of plant parameters, ;The actions also contain steps requiring more  ;

complex reasoning or analysis. ,j

_The Abnormal Operating Procedure are an integral cart of the overa11' FSV emergency preparedness program. _ The Abnormal Operating Procedure have been structured so as to facilitate the transition from Abnormal l Operating Procedure to the appropriate a RERP implementing procedure or event reporting procedure with minimal delay or confusion. In order to further aid with

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f7 classification-and reporting decision making,.an " Event and

?! l- Emergency l Classification Overview" procedure is provided at the Y back of this' document. This procedure discusses the -

> classification systems; provides' guidelines for event

' classification, serves as a-reference for pertintnt reporting or activation tables Jand provides a summary table that discusses reporting / activation requirements.

The. Abnormal--Operating procedure'are intentionally brief to be

. sui.taole for implementation. To provide the~ background and explanation required for study and understanding of the

  • procedures by the operators, separate'appendi:es have.been prepared. . The appendices are indexed'and titled to correspond to;the Abnormal;0perating 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.

II. FORMAT:

Each Abnormal Operating-Procedure is presented in a symptom -

% action matrix-format consisting of symptoms, and operator L actions. Symptoms include plant conditions, alarms, and h indications that are associated with the condition. The ..

L operator actions are few', and as brief as possible.to stop the

, degradation of conditions, mitigate their consequences, and l allow. the operators -time to evaluate the situacion.

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The sympto'm . action matrix presentation format was selected for a number of reasons, as--follows:

A. It provides an abbreviated presentation of symptoms and operator actions which must be readily usable -

during an abnormal plant con'Jition. *

'B.- .

allows specific operator actions to be identified against specific alarms or plant conditions; and, C. -It does not preclude the- use of precautionary notes .

or caution statements where deemed appropriate. ,

l An additional feature of the symptom-action-Matrix fo'rmat- is -

l_ that it permits' shift supervisor and reactor operator actions to

-l- be Identified-as-follows:- -

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(f III. ADMINISTRATIVE RULEi:

.A.- It shall be the responsibility of the Shift Supervisor or the reactor. operator-to terminate:defueling activities down when the. safety of-the reactor is in jeopardy or a.

reactor-protection circuit setpotid has been exceeded.

B. It_shall be the-responsibility of the Shift Supervisor to-

-investi. gate an unexplained count' rate change and report i

.his-findings to the. Station Manager or Superintendent of -

l Operations.

L C ;- :It shall befthe responsibility'of;all employees to gafn a working knowledge of the Technical Specifications as they h .

apply to specific job requirements, and to take-'

eppropriate steps to assure compliance with them.

.. 'IV. ALARMS AND: NOTIFICATION OF EMERGENCIES:

A; The audible alarm system in the control room, referred to i

.in the procedure as_an'" alarm" or " common alarm", is an automatically-actuated annunciator' system with three distinct alarm sounds. They tee:

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-FORMlol372 22 3843

i= AOP INTRO Issue 56 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 4 of 5 Lv Public SerVlCO* Pusuc SERVICE COMPANY OF COLORADO O (1)

A " Siren" indicating reactor scram; I

i' (2). A " Bell" indicating loop shutdown, circulator trip; and, (3) A " Horn" indicating any equipment system abnormalities, and 1-09 alarm.

As required, the control room annunciator alerts the operathg staff to an abnormal condition in the plant.

The reactor operator has control over the duration and silencing of all alarms. .

B. The p,lant 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: ,

l (1)- Siren general alarm to indicate fire or other emergency.

(2) Yelping - radiation alarm.

l The plant emergency alarm is activated by operating

. personnel H the control room. All personnel, upon hearing the alarm, shall report immediately to their

- - 'pte-assigned emergency station for accountability and -

further instructir9s 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 a; possible, announce over the'Gai-Tronics system, the nature of the emergency,

  • and any pertinerA instructions to the plant personnel.

V. C0teit:NICATIONS:

During an emergency situation requiring removal of plant -

personnel- from the plant to either an onsite or offsite location, comuunication lines shall be esta'alished as described in the Radiological Emergency Response Plan.

VI. SUPPORT PERSONNEL:

In the event that any emergency cor:dition exists which requires notification of plant management, the Shift Supervisor, or his designee, shall notify a r. ember of plant management (denoted in the Control Room implementing procedure), who shall be responsible for the notification of the remaining plant management personnel and department supervisors.

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Issue 56 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 5 of 5 4, -

PubllC SerVICO* PUBUC SERVICE COMPANY OF COLORADO

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AOP A n )

Issue 58 Page 1 of 2 Q\'.-('"

4., 1, -. PubilC FORT ST. VRAIN NUCLEAR GENERATING STATION h  !

$9tVIC98 Pupue saRVICE COMPANY OF COLORADO  !

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AOP-A 8ssue $8 Page 2 or 2 (A) totSit1R LSM-tJAs cg SYMPTOM-ACilON MAIP.lX 4 I -

5 SvMPIONS 8 I I I i 1.1 8 8 8 Primary Coolantt 8 ACTIONS IMoisture High, 5 I IME-9306 or i I IME-9307 on i I 8I-058, 3-1 8 I I $

$ OPf ftATOft ACilOft 8 8 82.1 I I I t il Primary Coogant t xx e I moisture sevet is abnormell t I AM increasing with no I e i known cause, LtfB attempt i e I to Identify source of f i t in leakage, f 8

, I I I I 2.2 I I I ff EES section is I XX t

Taentarie.e as source or i

, I moisture LHG estabt isti I I

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! I ope ra t ing loop per I I I SOP 22-01. 8 I

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AOP. APP A j c '

Issue 58 j age 1 of 1 j A Public FORT ST VHAIN NUCLEAR GENERATING STATION Pusuc sanvece courAmy or cotonAno 1 NGF Service *

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INTRODUCTION Section A of the Abnormal _ Operating Procedures deals with water leaks into the Primary Coolant System.

In the following section, each step of the Aonormal Operating ,

Procedure is discussed to aid the operator in understanding its  ;

basis. To facilitate relating each step to its discussion, each AOP step is repeated and urJerlined to set it off from the discussion  ;'

that follows, DISCUS $10N OF SYMPTOMS .

SYMPTOMS' i.1 Primary coolant inoisture level high. HE-9306 or ME-9307 on 1-05B, 3-1.

4 OPERATORACTQN 2.1- IF primary coolant moisture level is abnormal AND increasing with no known cause. THEN attempt to identify source of in-leakage, p If the' rate of moisture increase is low, as would be the (j . case with a small leak, source identification wivl be difficult'at best. The. operation of tv,e cie:alator -  ;

auxiliaries should be checked and corrected if that is the source of the moisture ingress.

NOTE'r Cooling with a flooded reheater outlined in Steo 2.2 yequires permission of Superintendent of Operations or Station Manager.

2.2 IF EES section is identified as= source-of moisturr THEN- -

establish cooling via reheater of operating loop per '

-SOP 22-01.

This action will isolate-the leak and permit continued -

' core cooling.

L 50P 22-01 describcs the necessary precautions and. -

procedures associated with coo)ing on L flooded reheater.

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g. Public FONT sT. VRAIN NUCLEAR GENERATING STATION ServlCO' PUBLIC SERVICE COMPANY OF COLORADO lO V TITLE: REACTOR SCRAM RESPONSIBLE (\ , AUTHORIZED FOR: , .[f [. Nd 4 &f ffne....B

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AOP-8 8ssue 58 Page 2 of 2 (B) -

REA_GIOR SCRAM -

SYMPIOM-ACitOM MATRlx 1 l l SYMPTOMS I l __ 1 1 I 1.1 -l 1.2 1 1.3 I I IStartup Count IMeutron Flux l Loss of Plant l l ACTIG'IS l Ra te H igh ( RMS-I Ra te o f Change l Power l I INot in RUM) lHigh (ISS-Startl I-03B I I I I-038 lup) 5-038 1 4-2, 5-2, 6-2 I I i 4-4, 5-4, 6-4 I 4-3, 5-3, 6-3 I I I I I I I I I I I I I OPERATOR ACTION l i l i 1 2.1 1 1 1. I I insert manuat sc ram. I xx I xx I xx I I I I I I I 2.2 I i I i I Ensure reactor internal I xx I xx I xx  !

I maintenance terminated. 8 l l l 1 I I I I I 2.3 I I I I I Ensure att Pcav openings I xx I xx t xx l I closed. I i I I i I i i i i I I I I I 2.4 I I I I I i Mon i tor Cri t ica s Sa rety I xx I xx I xx i l Tunctions per [OP's. I i I i I I I _1 1 9

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a A0P APP B

Issue 58 Page 1 of 2

(- Public FORT ST. VRAIN NUCLEAR GENERATING STATION

$9fVlC9' PUBUC SERVICE COMPANY OF COLORADO INTRODUCTION s

Reactor scram is the ultimate defense against any circumstance or condition th?.t threatens to damage the reactor core and release radioactive fission products. Reactor scram is initiated automatically by the Plant Protective System (PPS) in a number of situations described in the following discussion of symptoms.

The specific PPS actions that are initiated by reactor scram are as follows:

1. The control rod brakes are de-energized. .

2 Power to Rod Drive Motor Control Centers (N-9225, East and N-9226, West) are interrupted (K49-51 and K48-50 green lights on - Board I-10).

~

3. First-in scram annunciator and indicating light are '

actua+.ed, indicating which logic channels have tripped, A, B, or C.

DISCUSSION OF SYMPTOKS S;MPTOMS 1.1 Startup Count Rate High (RMS Fuel Loading) 1-03B 4-4, 5-c 6-4 This scram is actuated when either source range nuclear channel equals or exceeds a neutron countrate of 1.0E+5 counts /second with the Reactor Mode Switch not in the RUN position. The scram action is initiated by 1 of 2 logic tripi the Nuclear Start-up Channels I or II. .

1.2 Neutron Fiux Rate of Change High (ISS Start-Up) 1-038 4-3, 5-3, 5.-3 This scram is actuated as a result of Widt Range Nuclear -

Channels 111, IV or V equaling or exceeding a neutron flux rise of 5 DPM.

O FOAM (o)372 22 300

. . AOP APP B l - i Issue 58 age 2 of 2

,. Public FORT ST. VRAIN NUCLEAR GENERATING STATION SerVlCO' PusuC SERVICE COMPANY OF COLORADO O

'A 1.3 Loss of Pl' ant Power 1-03B 4-2, 5-2, 6-2 Undervoltage detectors sense the voltage on all three phases of all three essential buses. Detection of voltage loss persisting for 30 seconds by 2 of the 3 detectors on 2 of the 3 busses will produce 2 of 3 scram channel trips, causing a -

reactor scram.

The accident of concern is the loss of outside power, and failure of one diesel generator to start. A scram is required to allow for heat removal with less than a normal complement of plant equipment. ,

DISCUSSION OF OPERATOR ACTION 2.1 Insert manual scram. . -

Insert manual scram following automatic scram as a backup to the PPS to insure a full scram. A manual scram can be inserted by operating the scram handswitch to the scram position, by depressing two of three push buttons on 1-49, or by placing the RMS (Reactor Mode Switch) to the off position, inward rod q motion and decreasing flux are observed to verify that tne scram is having the desired effect.

2.2 Ensure reactor internal maintenance terminated The operator should advise any personnel involved ir operations from the refueling floor that a scram has occurred and that fu-ther operations should be terminated until it is determined to be safe to proceed.

2.3 Ensure all pCRV openings closed - -

Openings through the PCRV should be closed as soon as possible to prevent the out leakage of primary coolant and potential release of activity.

2.4 Monitor Critical Safety Functions per E0P's.

If the operator verifies that any critical safety function is not being met, the operator will proceed to appropriate E0P. t

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FoRMtD)372 22 3643

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. AOP 0-1 Issue 56 g l.,

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%)7 ServicG8 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 1 of 2 PUBLIC SERVICE COMPANY OF COLORADO

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AOP D-1 issue 56 Page 2 of 2 (0-1)

SIPICLE CIRCULA10R I RI P OR ONE C 8 8tCUL A T C T R I P I N E ACH 100P SVMPIOH-ACiiOM t'.AI.RE 5

I I SNMPIDFS l i

4 i 1.1 8 1.2 8 1.3 4 i

[ IHelsum IHelium fHelium I I ICirculator i ACTIONS ICi rcul a tor ICircolator

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l ISpeed High 8 Pene t ra t i on Stoss of f I IPressure High IBeareng Wateri I .I IIA 105A 2-2 8 (1A 105A 1-1 11A 105A 4-2 I

8 IIB 105A 1-3 118 105A 4-4 518 105A 2-4 8 8 11C 105D l-1 81C 105D 4-2 I1C 105D 2-2 6 81D 105D 4-4 IID 105D 4-4 I 8 81D 105D 1-3 I I I f I OPLRATOR ACTJOM . I e t '

8 t i 8 I i 1.1 Ensu re I t penetration inter- t I XX l l I $ I i space t,tock valve i I closed. I I f f i

8 1.2 Ensure tripped I 8

  • I I I B i circulater water I I speed, water turbine i I i 8 j

I intet, and water I I I B 9 XX 3 J turbine outlet block 8 8 f f I t valves close. I 8 8 8 l~l.3 Verify / set i I XX f 8 ci rculator brake and i I 8

I I i

I seat and isolate i i KX I I c i rcula tor 1 I f

8 auxiliaries, I i f 8 i

1. 4 Mon i to r c ri t ica t 3 4 t XX e XX 1 t safety functions per . XX l I I I I f_ LOP's.

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AOP APP D-1 Issue 56

('r A Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 1 of 3 YOF Service

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INTRODUCTION Circulator trips are initiated by the Plant Protective System (PPS) to protect the circulators and associated equipment against various auxiliary equipment and control system failures.

When the cause of the trip is loss of bearing water pressure, all the circulator auxiliaries are isolated. In this event, the circulator 4 brake is_ applied when the speed has coasted down to 700 rpm. Twenty seconds later, the static shaft seal is automatically applied.

DISCUSSION OF SYMPTOMS .

1.1 Helium Circulator Speed High t Speed senscrs monitoring shaft speed actuate the circulator trip logic system when circulator speed exceeds ~

'8,800 rpm. Actuation of at least two of the three sensors

  • is. required to cause trip.

Excessive circulator speed is an indication of a speed controller failure or other circulator system failure necessitating rapid shut 6cwn of the circulator. The speed sensing system response and trip setting are chosen so that, for the case of the maximum overspeed situation

'j :.

.possible (loss of restraining torque), the circulator speed will remain within design limits. -

1.2 Helium Circulator Penetration pressure High.

Pressure exceeding 810 psig in the circulator penetration

.will actuate pressure switches. Actuation of at least two of the three switches is required to cause trip.

Circulator penetration overpressure is indicative ~of a-

  • pipe, rupture within the penetration. A circulator trip is initiated and the purified helium pressuriz hg line to the

-penetration:is closed to prevent moisture be;kflow into the purified helium system.- The relief.of the .  ;

overpressure is handled by the circulator penetration l relief valves. The trip point is set above normal .;

operating pressure but below the circulator penetration '

relief valve setting. '

1.3 . Helium Circulator Loss of Bearino Water.

Pressure switches sensing the differerce between primary coolant pressure and bearing water pressure actuate at a -

differential of 475 psid. Actuation of two of the three switches is required to cause trip of the steam drive and v prevent automatic water turbine start.-

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FORMIDl372 22 3M3 I

. AOP APP 0-1 Issue 56 89' O 4~r A Public FORT ST. VRAIN NUCLEAR GENERATING STATION 47 Service

  • PUBUC SERVICE COMPANY OF COLORADO O NOTE After a loss of normal bearing supply (loss of all i three pumps in a loop) the NBW isolation valves

(-1) and the flow control valves close to prevent re-establishing normal bearing water on top of back-up bearing water. These valves must be shut (on controller /handswitches) in order to re-open.

Loss of bearing water is potentially damaging to the helium circulator. The trip point is sat to ensure that .'

the normal and auxiliary bearing water sources are

. available; if not, the circulatnr is tripped. The line to the bearing water accumulator opons automatically, due to .

reversal of differential pressure across a check valve, to allow use of the stored water during circulator coast down.

-O!SCUSSION OF OPERATOR ACTION -

L 2.1 Ensurepenetrationinterspaceblockvalveels& l High penetration pressure indicates a bearing water pipe leak in the penetration. The purified helium penetration interspace block valve is shut automatically to prevent water from backing up the line and getting into the .

purified helium system. The operator acts as a backup to

.O. , the PPS.

2.2 Ensure Tripped Circulator Water Soeed, Water Inlet, and ~~

Water Outlet Block Valves Close.

This step verifies proper circulator shutdown by PPS.

2.3 Verify / Set circulator brake and seal, and isolste circulator auxiliaries.

1) The circulator must coast down to less than 700 rpm before brake will set. The static seal is inhibited from setting by a 20 second time delay after the brake is applied.

The static seal vill be damaged if applied while the shaft is turning. The circulator brake is provided to stop the shaft when it is necessary as a result of dynamic seal or bearing malfunction.

O 2) Isolate circulator auxil' aries.

By isolating circulator auxiliaries, any leakage in L bearing water piping or buffer helium piping will

( be stopped.

O FORM (D) 37.."2 3843

! . . . AOP APP D-1

    • Issue 56 Page 3 of 3
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  • Public FORT ST. VRAIN NUCLEAR GENERATING STATION SGIVlC9' Pustic sFAVICE COMPANY OF COLORADO O 2,4 Monitor Crit'. cal Safety Functions Per E0P's, Monitor critical safety functions per E0P's and perform steps of E0P's as required.

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RADIdLOGICALEMERGENCYRESPONSEPLAF-IMPLEMENTING i

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ISSUE EFF.ECTIVE NO. . SUBJECT NUMBER DATE RERP-ALERT RERP-Implementing Procedurt -

ALERT 1 07-24-87 -

RERP-SITE AREA RERP-Implementing Procedure -

, Site Area Emergency 2 05-09-88

.RERP-GE RERP-Implementing Procedure -

General Emergency 1 07-24-87 , _.

RERP-NOTIFICATION' RERP - Implementing Procedure:

Follow-up Notifications 3 11-14-88 RERP-CED RERP. Implementing Procedure -

Corporate Emergency Director . 1 07-24 .

4

/ RERP-CR. RERP - Implementing Procedure -

t Control Room 14 08-08-90

-RERP-ECP RERP-Implementing Procedure - . _ .

Activation of the Executive <

Command-Post 14 06-23-89 ,

RERP-FCP- RERP-Implementing Procedure.

Activation of the For,;ard Command Post 16 11-89 RERP-PCC RERP-Implementing Procedure -

Activation of the Personnel

-Control Center 20 04-05-89 ,

RERP-SEOC RERP-Implementing Procedure Activation of the State Emergent.,

Operations Center 12 04-12-89 i

l RERP-- RERP-Im-lementing Procedure -

l TRANSPORTATION Transportation 2 02-06-91 RERP-TSC RERP-Implementing Procedure:

Activation of the Technical Support-Center 21 05-16-93 y RERP-RECOVERY. RERP-Implementing Procedure ,

Recovery Operations 2 07-31-88 4

' r34HD1372 22 3M3

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BOOK 1 .

Public FORT ST. VRAIN NUCLIAR GENERATING STATT/Q6/91 O $9fVICe* Pusuc SERVICE COMPANY OF COLORADOage 2 of 2 O

RADIOLOGICALEMERGENCYRESPONSEPLAN-IMPLEMENTING

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O FORM (DI372 22 364

,. RERP-TRANSPORTATION

!ssue 2 A Public FORT ST. VRAIN NUCLEAR GENERATING STATIOffage 1 of 14

%)F Service' rusuC SERVICE COMPANY OF COLORADO p(/'

r TITLE: RERP-!MPLEMENTING PROCEDURE - TRANSPORTATION RESPONSIBLE AUTHORIZED

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THORIZED h k$ BY: ,

PORC EFFECTIVE -

REVIEW PORC 919 JAN 3 01991 OATE 2.-b,.C}l ~

DCCF NUMBER (S) 4 l-OoM .

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VER!rY ISSUE STATUS WITH SITE DOCUMENT CONTROL CENTER PRIOR '

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i FORM 10372 22 3642 I _ _ - __

e RERP-TRANSPORTATION Issue 2 ,

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O $9fVlCO*Puruc saRVICE COMPANY OF COLORADO t /-

V l TABLE OF CONTENTS l 1

i 1.0 PURP05E...................................................... 3

2.0 REFERENCES

.................................................. 4 3.0 DISCUSSION .................................................. 4 4.0 PREREQUISITES................................................ 6

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5.0 LIMITATIONS........................................... ...... 6 -

6.0 PRECAUTIONS.................................................. 6 7.0 EQUIPMENT,................................................... 7 J 8.0 PROCEDURE.................................................... 7 ,

I 9.0 COMMITMENTS.................................................. 9 10 . 0 ATTACHM E NT S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10

,\ 10.1 Attachment A - Transportation Situation Receipt of ld .

No t i f i c a t i on Fo rm . .-. . . . . . -. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 ,

10.2 Attachment B - Response Decision Matrix................ 12 ,

l_ 10.3 Attachment C - NRC 1-Hour Notificattan Form............ 13 -

l 10.4 Attachment 0 - TRT Equipment List...................... 14 x

FORM tD1372 22 3543 y -.. --,e.-, - - -

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  • RERP-TRANSPORTATION Issue 2  !

Public, FORT ST. VRAIN NUCLEAd GENERATING STATION Page 3 of 14 OService* eunuc sanwes comeAmy or cotonApo O 1.0 PURp0SE l

i NOTE: Control Room notification requirements for non-emergency l ano eme gency classifications are identified in RERP-CR, 1.1 ,4 'tey objective of this procedure is to ensure wpropriate actions are taken, or are Deing taken, by either PSC or respective state and local emergency response personnel to ensure the health and safety of the public and_ environment in the vicinity of a transportation situation is not endangered, ,

1.2 This procedure provides guidance to Public Service Company -

of Colorado (PSC) employees on actions to take upon receiving notification of a spent fuel shipping l transportation situation after the shipment has left PSC property. .

1.3 This procedure identifies key " players" and teams by "

shipping program titles. The Shift Supervisor and Control Room will have in their possession during any given

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shipment, a listing of the appropriate on-duty personnel ,

and contact numbers corresponding to the titles utilized  !

within this procedure, 1.4- This procedure will assist the Shift Supervisor,- Control ~ '

. Room staff and shipping program personnel in making decisions concerning appropriate PSC response to any given ,

transportation situation reported. Attachment B to this i procedure contains a decision matrix to assist in - ,

determining appropriate PSC re ponse to any given  ;

transportation situation, However, each situation-will be  :

analyzed on a case-by-case basis and the final decision on l response actions will remain with PSC management 1 personnel.

1,5 This procedure.will also ensure that appropriate Media Relations personnel are kept informed of any situation with_ complete and accurate information.for dissemination to the media.and general public, L _l 1.6 The driver / escort team and/or shipping agent dispat.er L l are required to inform PSC of dela" while in transit. In l l 'such an event, the on-duty shippirt wordinator shall be-l immediately informed. Any notifica. ions to governor's +

c .l designees and the NRC for delays fall outside the scope of l this procedure, l

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2.0 REFERENCES

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2.1 RERP-PLANT

- 2. 2 RERP-CR PSC DEFUELING/ DECOMMISSIONING PUP,LIC INFORMATION PLAN  !

2.3 3.0 01SCUSSION-l 3.1 Tts defueling campaign associated with Fort St. Vrain will involve numerous shipments of spent fuel to a storage

  • facility. All of these shipments undergo a thorough -

inspection (both mechanically and radiologically) prior to 1 leaving PSC property. Regardless of these precautions, a  ;

situation involving a spent fuel shipment can occur.  !

These situations could include shipment delay in route due . .i to weather conditions, law enforcement, mechanical breakdowns, or public protest; situations to the transport.

vehicle; or even a severe situation involving an unlikely .

breach of the shipping cask containment. Each situation has the potential of impacting the general public and environment, thus causing a delay in the completion of the spent fuel shipping program. PSC's response to, and  :

O control of, each situation, especially in the area of

.-() ,

public safety, information, and perception, is essential

.to ensure a safe and timely completion of FSV reactor '

defueling.

3.2 At all times while responding to a transportation situation off of PSC property, the PSC Transportation Response Team (TRT) is in an assist position. The team is there to assist the local response forces, as needed, and

-to gather an independent set of data concerning the situation for corporate records . At no time will the TRT make any decisions.concerning local response actions, ,

-however, the TRT may provide recommendations, if asked. 1 e

FORM (D)772 22 3843

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3.3 The TRT will typically be comprised of the following positions and corresponding responsibilities:

3.3.1 TRT Coordinator (1): Responsibilities include; Command and Control of all PSC response personnel ,

and actions, Communications to F5V and PSC Corporate persennel concerning the situation, Liaison between TRT and local response personnel.

Alternate media /public spokesperson.

TRT transportation and equipment coordination. ,

_s 3.3.2 TRT Assessment Specialist (1 or more):

Responsib111 ties include; ,

Radiological assessment, Mechanical / Damage control assessment, l t

Assisting local response forces, as directed by the-

-- L TRT Coordinator. ,

NOTE: There may be more than one individual responding as a TRT Assessment-Specialist. Differentdisciplines(i.e., e health physics background, cask engineering background, fuel engineering background, etc.) may be sent with the .

TRT depending on given conditions of the situation. 1 3,3.3 TRT Media Relations Representative (1 or more):

Responsibilities include; Primary media /public spokesperson, Assisting with communications to FSV and PSC Corporate personnel, o

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$9rVIC9' PusuC ssRVICIE COMPANY OF COLORADO l 3.4 A Communications-Assessment Team (CAT) will be established, if needed, in the Technical Support Center (TSC) at the FSV site. The TSC contains sufficient I communications capabilities within the PSC network, to the  !

NRC (ENS and HPN phones) and to state and local egencies.

This team will be comprised of various technical  !

assessment, communications and management personnel. The l CAT will have the capability to obtain all necessary  !

documentation and personnel to assist in evaluating  !

situations concerning shioping cask integrity and I situation recovery. The CAT will also be responsible for -

ensuring all TRT assessment informatiun is passed on to appropriate personnel and agencies and assisting corporate .

Media Relations personnel in formulating any necessary media / general public information rolease5. ,

i 4.0 PREREQUISITES .)

4.1 FSV/PSC has received, and has validated, a notification ',

from either_ a local response agency, a bonafide shipping notification contact, or the contract shipping company of a situation involving a FSV spent fuel shipment. '

Attachment A to this procedure contains a notification -

l receipt form to be used for-such notification receipts.

S.0 LIMITATIONS ~

S.1 None I

6.0 PRECAUTIONS 6J All notifications made to PSC concerning a transportation r situation should be verified to be valid prior to L initiating response actions. This vain ';on can be .

3 performed using one of the following y delines:  ;

6.1.1 Call contract shipping dispatch for verification communication to driver.

6.1.2 Call respective state shipping notification contact for verification.

6.1.3- Call respective state law enforcement agency (if dif ferent f rom step 6.1.2).

6.1.4 Call respective local response agency (if known),

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  • - '- RERP-TRANSPORTATION Issue 2 Public. FORT ST. VRAIN NUCLEAR GENERATING STATION page 7 of 14

$9FVICO' PusuC suaveCu COMPANY OF COLORADO O

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6.2 The Shift Supervisce and Control Room personnel should be  !

re6dy to toentify all personnel making notifications and I note any particular identifiers heard during the notification (background noise, background music, voice specifics such as; male / female; speech problems; etc.).

l The Transportation Situation Ree.eipt of hotification Form (Attachment A) provides space to note any of these items.

6.3 All media / general public information releases will be i coordinated through PSC Media Relations Department personnel.- - ,

j 6,4 Any event for which a news release is planned or another -

government _ agency has been notified must be classified as '

-a 4-hour non-emergency as a minimum.

7.0 -EQU!PMENT -

7.1 Equipment available to be dispatched with the TRT is l identified in the TRT Equipment List (Attachment 0 to this procedure).

-8.0 PROCEDURE

.8.1 Shift Supervisor / Control Room (SS/CR) Actions 8.1.1 The SS/CR will obtain and fill in a copy of Attachment A to this procedure upon receiving a

.l. notification of a transportation situation.

8.1.2 The SS/CR should: verify situation notifications ,

with the trucking dispatcher as they have direct communications capabilities with the individual trucks.

8.1.3 The-SS/CR will.then notify the on-duty FSV Shipping l: Coordinator to inform him/her of the receipt of-l notification and to assist in determining l classification.and notifict. tion requirements, if any,- .?

l 8.1.4. The SS/CR will initiate any required non-emergency or_ emergency notifications per RERP-CR.

l 8.1.5- Notification of delays (no media concerns) can be l routinely expected. Upon receipt of such l notifications the SS/CR shall inform the on-duty l shipping coordinator and no further actions are l required of-the SS/CR.

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,- A Public. FORT ST. VRAIN NUCLEAR GENERATING STATION Page 8 of 14 47 Service

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(V 8.2 FSV Shipping Coordinator (SC) Actions 8.2.1 The SC will review the decision matrix (Attachment B) with the Shift Supervisor upon receiving the appropriate information from the SS/CR.

8.2.2 Based upon the decision matrix and all pertinent information known concerning the transportation situation, make or recommend an appropriate response action. ,

8.2.3 Verify the SS/CR has made a decision of non-emergency or emergency classification, and has made, or is making appropriate notifications per RERP-CR, as needed.

8.2.4 Based upon the decision made, notify the on-duty TRT Coordinator and/or PSC Media Relations Department personnel for briefing and/or deployment.

8.2.5 If dictated bj the situation, respond to the FSV Control Room to assist the SS/CR with additional

/^ l receipts of follow-up notifications. The SC may eventually join the CAT in the TSC, if this team is ~

formed.

l 8.2.6 Make any notifications of delays totaling 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> l or greater per shipment, to appropriate governor's -

I designees and the NRC. These notifications are i controlled and documented in accordance with the I applicable spent fuel shipping procedure.

8.2.7 In the event of Step 8.2.6, inform the SS that

, governor designees have been contacted and that a l 4-hour non-emergency notification must be made.

8.3 Transportation Response Team (TRT) Deployment Actions 8.3.1 The TRT Coordinator will determine the most efficient means of transportation to the situation  ;

site and make appropriate arrangements for such transportation.

8.3.2 The TRT Coordinator will ensure all required members of the TRT have been notified and arrange for a pre-deployment briefing location and time.

8.3.3 The TRT Coordinator will ensure necessary equipment fm l per At.achment 0 is checked and packed for Q transportat'on to the situation site.

1 FORM to)772.J2 3643

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  • FORT ST. VRAIN NUCLEAR GENERATING STATION Page 9 of 14

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  • rusuC saRWCa COMPAM OF COLORADO 8.3.4 The TRT Coordinator will receive last minute instructions /information concerning the situation from the SC or CAT prior to deployraent to the situation f.ite, j 8.3.5 Necessary communicatia , links with the SC/ CAT will l be established whent ' possible while enroute and at the situation site. ,

8.3.6 At the situation site, TRT members wil? perform duties as outlined in Section 8.5. ,

-I 8.4 PSC Coinmunicatiens-Assessment Team (CAT) Actions 8.4.1 PSC managemer t personnel will notify and assemble ,

-necessary technical assessment and communications personnel in the Technical Support Center (TSC) at e the Fort St.-Vrain site. '

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8.4.2 Necessary communication, links with corporate and

~* state agencies associated with the transportation situation will-be established, whenever possible.

-w 8.4.3 Ensure PSC Media Relations personnel are kept fully

' L informed of the situation.

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8.4.4 Keep regulatory agencies informed of the situation. <

8.5 Transportation Response Team (TRT) On Scene Actions-8.5.1. The.TRT Coordinator will identify him/herself to the incident Comm' der'(or cognizant response

, agency representative) or.the shipment drivers at the situation scene'and report that the TRT is available for any assistance.

8.5.2 The TRT Coordinator will direct and control all PSC personnel ~at the scene. 7 c

L 8.5.3 The TRT Media Relations Representative (TRT Coordinator-if media representative is not. '

,. available)'will obtain.a briefing from'the local >

l response media representatives as to_what has already been' released to the media and keep appropriate counterparts in the CAT or corporate contacts informed of.any-changes in the situation.

9 .' O COMMITMENTS 9.1' None a

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$4fVIC9' Pusuc saRVlCE COMPANY OF COLORADO rN.-

U 10.0 ATTACHMFNTS l 10.1 Attachment A - Transportation Situation Receipt of l Notification Form 10.2 Attachment B - Response Decision Matrix l 10.3 Attachment C - NRC 1-Hour Notification Form i 10.4 Attachment 0 - TRT Equipment List k

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- Attachment A i

  • Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2  !

Page 11 of 14  !

Service

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TRANSPORTATION SITUATION RECEIPT OF NOTIFICATION FORM j l

Date: Time Call Received:

Name of Caller: Organization:

Phone Number of Caller: Location of Caller:

Caller Identifiers (background noise, music, etc.): .;

Problem / Notification:

l lWasvehicledisablingdeviceengaged? Yes No Unknown ,

Exact Location of Vehicle: e

. 4 Radiological Problems:  ;

Current Weather Conditions at Vehicle:

  • 1 m . L Shipping Company Dispatcher notified for verification:

-(name) (time)

On-Duty shipping Coordinator notified:

(name) (timeT-Station Management notified:

(name). (time)-

c Classification Declared at time: Icheck appropriate line)

, s NO CLASSIFICATION' FOUR HOUR NON-EMERGENCY EVENT

, ONE HOUR NON-EMERGENCY EVENT NOTIFICATION OF UNUSUAL EVENT 1 ALERT ,

Completed by:

.- (signature)

T.

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RERP-TRANSPORTATION Attachm2nt B

  • FORT ST, VRAIN NUCLEAR GENERATING STATION j$$ye 2

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O l RESPONSE DECISION MATRIX l Coding: M - Mandatory Action X - Recommended Classification l 0 - Optional Action blank - No Action Needed I - .

l l SITUATION I1l2l3l4l5l6llAlB1Cl01El ll l lTruck Delay a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> l l 1 Il l ii ll l i I i l l l l lXlITI lTl I 'l l[_no_mediaconc6rns) l~l-l-l l 1 Truck Delay 2 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> l l 1 1Xl ll - llI l T lI T l' T lI T lI T lI -

1-li~l-l-lTl l'I T Tl T lI -l l--ll 1

l(with media concerns) l l Truck Malfunction l l l l l l(cask secure) ,

i 1 i 1 l lPublic Protest l l T l--~ll-ll I T I T . T I T ll T lI l

1 l l(with media coverage)I l Truck Accident - No injurieil~~I~~I~~~I'~~FlTl ITlITlTlI I il - l l l I l l l l(no media coverage) l ~

l l Truck Accident - No Injuries l ll - ll T lI - l l - ll ll T ll T ll T ll "~~ll~l l l l(with media coverage) l l Truck Accident - Injuries l~~~I l l ~l l ~l l T ll-l1 l1Il T ll T lI T 0 l T lI l 1 l 1 l l Cask out of Position ll ~~l l ~~ l l ~~I 1l l--~l T l l-- l1ITITlTiTlTi O Ii 1-~"~1 ~ I l - l I~" I l T I1T I I T l IT l! T ;,

V I ITire Involving Cask l l lTI l l ll

  • ll (breach no determined) I~'~l l l l l uAbnormal Radiation Levels l T ll l l l llll T ll T lI T lI TI l T L ,

l Reported from the Cask I I l l ~~~ l ll Xl lI T lI T lI TI l T lI T ll l l Cask Breached I l l l

!! Notification':fLost I lShipment While in Transit

!-'- -~~ -- T!-- T T!T!--~lT!

l - l -~- l -- l l l jfiotification of Recovery of I 1 l l lXll - -ll l l T lI T lI lT l ~ '~ll--~l l i llost Shipment l 1 l

l l Actual Loss,Thef t,0tversion ITl-~~l '-ll I l--l lllTlITlTl---llTl I l I I l l lor Sabotage of a Shipment l___,l _ l__,l _ l _ l _ l_l,_,_i _ l _ i _ l _ 1 l CLASSIFICATION RECOMMENDATION RESPONSE RECOMMENDATIONS l

  • 1 - ALERT A - Inform Shipping Coordinator l
  • 2 - Notification of Unusual Event B - Inform PSC Media Relations l
  • 3 - 1 Hour Non-errergency Report C - Inform On-Outy TRT l
  • 4 - 4 Hour Non-emergency Report Coordinator i
  • 5 - Notification to the NRC - 1 Hour D - Dispatch TRT to Scene 1 (Attachment C) E - Assemble CAT l
  • 6 - No Classification Required l
  • Make appropriate notifications per RERP-CR, D

(U FORM 1o1372 22 364

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,*e l Public FORT ST. VRAIN NUCLEAR GENERATING STATION Attachment C 155ue 2 Page 13 of 14 SGIVlCO' PUBUC HRVICI! COMPANY OF COLODADO O

I .RC 1 HOUR NOTIFICATION FORM l RAVE CALLER REPEAT INFORMATION FOR ACCURACY:

1 Date:

l Time:

I Caller's Name:

l Fort St. Vrain, Unit #1 (Region 4) .

I -

l This report is being made purscant to 10 CFR 73.71,1eporting of l Safeguards events. ,

I l EVENT DESCRIPTION: At (event time) on _

l Fort St. Vrain experienced the following:

~

) (Circle one): Discovery of the loss of a spent fuel shipmsnt.

l Recovery of a previously reported lost spsnt fuel i shipment. -

l Any Othar Details: _

l__

i

( IT6TIFICAT10t45: .

l Name of Contact _ . _,, l Tide _

l 3 hipping Coordinator: I l l .. . .

l. __l l NRC Operations Centeri 1 l l (ENS or 9-1-301-951-0550) l l 1 I I ~

I Plant Management: l l l I l l Other: l l l 1 l O

EORM tot 372 22 3643

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  • RERP-TRANSPORTATION
  1. Attachment 0 )

'p O- FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 i PUD llC Service

  • Pusuc sanvics comeAmy or cotonApo Pa9e 14 of 14 l

[

,v TRT EQUIPMENT LIST The.following is a list of available equipment for response to a l transportation situation.

Stored in TSC:

l Company Handheld Radios l Radio Belt Holders l- Spare Radio Batteries -

l Stored-in TRT Response Trunk:

Portable Radio Battery Chargers (115 VAC)

Clip Board with paper .

Box of Black Ink Ball Point Pens Box of #2 Lead Pencils '

Box of Red Ink' Ball Point Pens I Colorado Road Map i I Wyoming Road Map l Utah Road Map' -

I Idaho Road Map

.- / Complete set of Anti-C's F 0 k)./

Box of Disposable Gloves ~'

Set of Shoe Covers

-Plastic Sample Collection Bottles

-I 1 Rolls of Radiological Boundary Tape / Rope  :

1 1 Radiological Boundary Signs .

Battery Operated t.antern l Spare Lantern Battery i Pair of Binoculars 25 foot Tape Measure l Response Team Hard Hats l Response Team Safety Vests >

l Stored and Maintained by Health Physics / Emergency Planning: ,

ll Eberline RO-2 Radiac Equipment (or equivalent) 4 i Eberline RM-14/15 Radiac Equipment (or equivalent) l Extra RM-14/15 Probes (GM Tubes) l- Cellular Telephone Kit 1 Camera and Film-O-

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