ML18005A712

Forwards Rev 3 to Emergency Procedure PEP-101, Emergency Classification & Initial Emergency Actions. Rev 14 to Emergency Plan Completed.Training on New Emergency Action Level Flow Paths Provided to Operators

ML18005A712
Person / Time
Site:	Harris
Issue date:	11/14/1988
From:	Watson R CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML18005A713	List: ML18005A712
References
CON-NRC-649 HO-880228-(O), NUDOCS 8811300508
Download: ML18005A712 (24)

Text

. ~ACCELERATED DI

'BUTJON DEMONSTR iTION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

DOCKET 05000400j>

ACCESSION NBR:8811300508 DOC.DATE: 88/11/14 NOTARIZED:

NO FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina AUTH.NAME AUTHOR AFFILIATION WATSON,R.A.

Carolina Power

& Light Co.

RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

/Z

SUBJECT:

Forwards Rev 3 to Emergency Procedure PEP-101, "Emergency Classification

& Initial...."

R DISTRIBUTION CODE:

A045D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: OR Submittal:

Emergency Preparedness

Plans, Implement'g Procedures, C

NOTES:Application for permit renewal filed.

o5ooo4oo >

RECIPIENT ID CODE/NAME PD2-1 PD INTERNAL: AEOD/DOA/IRB NUDOCS-ABSTRACT EXTERNAL: LPDR NSIC COPIES LTTR ENCL 1

1 1

1 1

1 1

1 1

1 RECIPIENT ID CODE/NAME BUCKLEY,B ERR/~RE EPB 10 MEG FIL ol NRC PDR COPIES LTTR ENCL 1

1 1

1 1

1 1

1 Sj A

9

'D R

NOZE LO ALL "RIDS" RECIPZERIS:

Sj A

PIZASE HELP US TO REIXKZ %MHZ.'XKI'A~'IHE DOCX3MEFZ CGNZROL DESK, ROC!M Pl-37 (EZT. 20079)

TO EZLIMINATE YOUR NME F$QM DISTRIBUTION LISTS FOR DOCtMEKS YOU DGNiT NEED)

TOTAL NUMBER OF COPIES REQUIRED:

LTTR 9

ENCL 9

~l I

c"

Carolina Power & Light Company NOV f41988 HARRIS NUCLEAR PROJECT P. 0.

Box 165 New Hill, North Carolina 27562 File Number'SHF/10-14030 Letter Number'HO-880228 (0)

Document Control Desk United States Nuclear Regulatory Commission Washington, D.C.

20555 NRC-649 CAROLINA POWER AND LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-400 LICENSE NO. NPF-63 Gentlemen:

In accordance with

10CFR50, Appendix E,

Carolina Power

& Light Company hereby transmits one copy of Shearon Harris Nuclear Power Plant emergency procedure, PEP-101, Revision 3,

Emergency Classification and Initial Emergency Actions.

With the approval of PEP-101, Revision 3,

implementation of Revision 14 to the Emergency Plan (PLP-201) has been completed.

Training on the new Emergency Action Level Flow Paths was provided to operators and to persons filling the positions of Emergency

Response

Manager, Site Emergency Coordinator, and Accident Assessment Team Leader during the period from September 29, 1988, until October 27, 1988.

Very truly yours, R. A. Watson Vice President Harris Nuclear Project MGW:lem Attachment cc:

Mr. W. H. Bradford (NRC)

Mr. B. C. Buckley Mr. M. C. Ernst (NRC) (w/two copies of procedures) 8811300SOS SSiil.4 PDR ADOCK 05000400 F

PDC MEM/H0-8802280/1/OSl

s88tbt VCl i

APR016 CAROLINA POWER 6 LIGHT COMPANY SHEARON HARRIS AWCLEAR POWER PLANT PLANT OPERATING MANUAL VOLUME 2, PART 5 PROCEDURE TYPE:

J4lDA IDLY PLANT CENCE PROCEDURE PEP

+

D '9 I H DIO NUMBER P

-101 TITLE:

EMERGENCY CLASSIPICATION AND INITIAL~ENCY ACTIONS REVISION 2 APPRO Sfgnasure

~b,7,

'Date IL Wllg l'INt I!fllfIII. SNEER Fes - 0'986

",OCui't,"ENY SERVIC;"."

Page 1 of 12

APR016

~

TABLE OF CONTEVES

'able of Contents List of Effective Pages 1.0 PURPOSE

2.0 REFERENCES

2.1 Emergency Plan References 2.2 Referenced Plant Emergency Procedures 2.3 Other References 3.0 RESPONSIBILITIES 3.1 Authority 3.2 Relief of Position 3.3 Designated Alternates 3.4 Duties 4.0 DEFINITIONS 5.0

" GENERAL

6. 0 INITIATING CONDITIONS 7.0 PRECAUTIONS AND LIMITATIONS 8.0 SPECIAL TOOLS AND LIMITATIONS 9.0 PROCEDURE STEPS.

10.0 DIAGRAMS AND ATTACHMENTS l.

Emergency Action Level Network 2.

Emergency Action Level Flowpath 3.

Fission Product Barrier Status Indications

~Pa e

2 3

4 4

4 4

4 5

5 5

5 5

5 6

6 6

7 7

8 9

10 11 PEP-101 Rev.

2 Page 2 of 12

A 0

List of Hffective Pa es

~Pa e 1'- 2 3

4 5

6 7 8

8'a 9

10ll 12 Revision 2

AC 2/1 through AC 2/9 AC 2/2 AC 2/6 2

AC 2/1)

AC 2/7 AC 2/7 AC 2/54 AC 2/2, AC 2/8 AC 2/4 AC 2/3, AC 2/4 AC 2/3 AC 2/5 consolidates AC 2/2 on page 9.

PEP-101 Rev.

2 Page 3 of 12

t P

C-

kFROI6

\\

~

~

~.

....~ --

1.0 PORPOSE The purpose of this procedure is to implement Section 4.1 of the SHNPP Emergency Plan> "Emergency Classification," which is a regulatory commitmcat Zt also implements corrective actions ia response to NRC Emergency Preparedness kppraisal Repott Number 50-400/85-09.

This procedure is to be used by thc Shift Foreman or his designated alternate ia the Control Room upon recognition of an off-.normal condition (as determined by direction from another procedure.

iaetrumcnt readings, direct observation, or reported events) to assist ia determining whether aa eveat should be cate-goriscd as'a emergency.

Once implemented, this procedure shall remain in effect uatil either:

1.

ha emergency is declared in accordance vith aa Emergency kctioa Level 2.

Thc determination furs been made by the Shift Foreman, or his designated alternate, that an emergency action level has aot been exceeded.

2,0 REFERENCES 2 I Emcr cnc Plan References I.

Sectioa 4 ~I~ "Emergency Classification" 2.2 Referenced Plant Emer enc Procedurce 1.

PEP-102, "Site Emcrgcacy Coordinator - Control Room" 2

PEP 103 ~

Site Emergency Coordinator - Technical Support Center" 3.

PEP-301 'Notification of Noa~&L Emergency Rcspoasc Organisations" 4.

PEP-403

~ "Performance of Traiaiag" 2.3 Other References I~

AP-036 ~ "Significant Event (Red Phone) Reports" 2.

kP-615, "NRC Reporting Requirements" pc.2C 7-9-Sk 3 ~

EOPWSFST, Critical Safety Function Status Trees" 4.

ERC-109, "Reports and Notification" 5.

SP-017, "Reporting of Physical Security Evcats" 6.

Nuclear Regulatory Commission Inspection Report Number 50-400/85-09

'EP-101 Rcv. 2/2 Page 4 of 12P ~"'.<

'APR016 7.

NUREG-0654t, "Criteria for Preparation and Evaluation of Radiological Emergency

Response

Plans aad Preparedness in Support o8'uclear Power Plants."

3.0 RESPONSIBILITIES

3. l

~Authorit The Shift Foreman on duty (or his designated alternate) has immedi-'te and unilateral authority to initiate and conduct this procedure.

He may delegate specific steps as necessary, but shall not delegate the final classification decision.

3.2 Relief of Position The Shift Foreman may be relieved by a designated alternate trained (in accordance with procedure PEP-403) to conduct this procedure.

3.3 Desi nated Alternates In order of succession, the designated alternates for the Shift Foreman are as follows:

1.

Roving Senior Control Operator 2.

Control Room Senior Control Operator I

3.4 Duties Until an emergency -is declared, the Shift Foreman has the following responsibilities relating to the Emergency Plan:

1.

Direct the activities of the Control Room staff.

2.

Recognize an off-normal condition as indicated by instru-ment-readings or observation.

3.

" Implement any Emergency Operating Procedures,Abnormal Operating Procedures, and Fire Protection Procedures as appropriate.

4.0 DEFINITIONS 2.

Fission Product Barrier' The fuel cladding,, reactor cool)nt system boundary, nr the containment boundary.

Fission Product Barrier Status a.

b.

Breached The fission product barrier is incapable of sufficiently retaining radioactive materials to protect the public.

~Jeo ard

- conditions exist that are likely to result in fission product barrier breach, but the barrier is intact at the present time.

PEP-101 Rev.

2 Page 5 of 12

j

~

f I

"V lg

OS4 0

2.3 Other References (continued) 6.

Nuclear Regulatory Commission Inspection Report Number 50-400/85-09.

7.

NUREG-0654, "Criteria for Preparation and Evaluation of Radiological Emergency

Response

Plans and Preparedness in Support of Nuclear Power Plants."

3.0 REPONSIBILITIES 3.1

~Authorit The Shift Foreman on duty (or his designated alternate) has immediate and unilateraL authority to initiate and conduct this procedure.

He may delegate specific steps as necessary, but shall not delegate the final classification decision" 3.2 Relief of Position The Shift Foreman may be relieved by a designated aLternate trained (in accordance with procedure PEP-403) to conduct this procedure.

3.3 Desi nated Alternates I

~'k In order of succession, the designated alternates for the Shift Foreman are as follows:

1.

Roving Senior Control Operator 2.

Control Room Senior Control Operator 3.4 Duties Until an emergency is declared, the Shift Foreman has the following responsibilities relating to the Emergency Plan:

1.

Direct the activities of the Control Room staff.

2.

Recognize an off-normal condition as indicated by instrument readings or observation.

3.

Implement any Emergency Operating Procedures, Abnormal Operating Procedures, and Fire Protection Procedures as appropriate.

4.0 DEFINITIONS/ABBREVIATIONS 1.

Fission Product Barrier - The fuel cladding; reactor coolant system

boundary, or the containment boundary.

2.

Fission Product Barrier Status-PEP-101 Rev.

2 Page 5 of 13

fl>

P

APR016 c.

Intact

- the fission product barrier retains the ability to protect the public from a baneful release of radioactive materials.

in NUREG-0654 4.

Unusual Event same as "Notification of Unusual Event" as defined in NUREG-0654

5. 0 Gggflldb None Applicable 6.0 INITIATINGCONDITIONS 2 ~

Entry into the Emergency Action Level network has been directed by any of the Emergency Operating Procedures, Fire Protection Procedures, Abnormal Operating Procedures, or any other procedure.

OR A Critical Safety Function Status Tree on the Safety Parameter Display System has produced a red or magenta output.

3 ~

OR Notification has been received from the Senior Member of the Security Organization.

or his designee that a "Security Alert" or "Security Emergency" has been initiated.

4, OR Conditions exist which, in the )udgement of the Shift Foreman, could be classified as an emergency.

7.0 PRECAUTIONS AND LIMITATIONS Implementation of this procedure does not constitute an emer-gency.

This procedure serves as a guideline to assist in comparison of plant conditions with Emergency Action Levels to evaluate whether an emergency should be declared.

2 ~

The highest emergency class for which an Emergency Action Level is currently met should be declared.

If an action level for a higher classification was exceeded but the indicated level currently has abated or the situation has been resolved, the higher classificarion should be

~ce orted ro the state,

county, and Nuclear Regulatory Commission in accordance with PEP-301, but should not be declared.

The notification must indicate the current classification, the period(s) of time that the higher classification existed, and the mitigating conditions that caused the emergency classification to be down-graded.

3 ~

Priority should be placed on saving lives and/or preventing excessive'xposure to personnel over saving equipment or preventing the spread of contamination.

PEP-101 Rev.

2 Page 6 of 12

APR016 4.

If the Nuclear Regulatory Commission Director of Site Operations is at the Control Room, Technical Support Center, or Emergency Operations Facility

, he should be consulted before downgrading the emergency class.

8.0 SPECIAL TOOLS AND E UIPMENT None Applicable 9.0 PROCEDURE STEPS Direct the senior on-site member of the security force to begin printing the Sheltering Assignments/Assembly Area Log which shows personnel currently on-site broken down by assigned Shelter/Assembly Areas.

2.

Enter the Emergency Action Level Network. Attachment 1, at the appropriate point:

a.

If you were directed to enter the network by another plant procedure, enter at the point specified by that procedure.

b.

If you are entering the network because a Critical Safety Function Status Tree on the Safety Parameter Display System has produced a red or magenta output. enter at point W.

c.

In all other cases, enter at point X.

3.

Proceed through the Emergency Action Level Network (Attachment

1) until the network directs you to either declare or not declare an emergency.

a ~

If the network directs you to "UPDATE CSF STATUS BOARD."

enter the output color of each Critical Safety Functi'on Status Tree (see EOP-CSFST) currently indicated on the Safety Parameter Display System in the data table provided on the network immediately below the instruction.

Use the data in this table to answer subsequent questions in the network logic.

b.

When the network directs you to "REVIEW ATTACHMENT 3",

refer to Attachment 3, "Fission Product Barrier Status Indications" for guidance on additional monitor, cnemistry and process indications that may be useful in detecting or confirming a breach condition.

C ~

When the network directs you to "UPDATE FPB-STATUS BOARD,"

enter the status of each fission product barrier in the data table provided on the network immediately below the instruction.

If you entered the network at points T, U, or V, use the stated condition(s) for the entry point(s) and any additional breach conditions indicated by review of Attachment 3. If you entered at point W, use the conditions determined from the immediately preceding logic PEP-101 Rev.

2 Page 7 of 12

l

~

OS4 9.0 PROCEDURE STEPS (continued) unless review of Attachment 3 indicates a breach condition for the same fission product barrier, in which case jeopardy, should be changed to breach for that fission product barrier. If you entered the network at point X, use the fission product barrier status determined from review of Attachment 3.

If the answer to the network question "EAL FLOWPATH REVIEWED" is NO, enter the logic of Attachment 2, "Emergency Action Level Flowpath" at point Z.

Proceed through the flowpath logic, reenter the network (Attachment

1) at point Y.

e.

Use the data entered in the fission product barrier tables and flowpath results to answer the subsequent network questions.

f.

If the network directs you to "EVALUATE AGAINST UNUSUAL EVENT MATRIX," proceed through the "Unusual Event Matrix" at the bottom of Attachment 1, then continue with the network.

NG5:

If off-site medical assistance is to be requested, notified or summoned to the site for an injured patient; and if the patient is contaminated per Section 4.0.3 of PEP-391 or the level of contamination cannot be determined or is unknown) then the patient is considered a "contaminated injured individual requiring off-site medical treatment" as listed in Attachment 1.

NOTE:

Preplanned removal of ERFIS and SPDS from service for maintenance or modification purposes does not require declaration of an Unusual Event.

In such case, notify the NRC Resident Inspector prior to" removal from service and again when the ERFIS/SPDS is returned to service.

If the network directs you to "DECLARE" any class of emergency, implement PEP-102, "Site Emergency Coordinator Control Room," or PEP-103, "Site Emergency Coordinator - Technical Support Center," whichever is appropriate, and enter the time below that point on the Attachment.

h.

If the network result is "NO EMERGENCY DECLARED,"

consult AP-036, ERC-109, SP-017 and AP-615 to determine whether the condition constitutes a reportable event other than an emergency.

PEP-101, Rev. 2/1 Page 8 of 12

~

~

OS4 4.

If conditions dictate a continued evaluation or reevaluation of Emergency Action Levels, reenter the network at point W or at other points as directed by procedures and repeat Step 3.

NOTE:

If the NRC Director of Site Operations is available, he should be consulted before downgrading an emergency classification.

10.0 DIAGRAMS AND ATTACHMENTS l.

Emergency Action Level Network 2.

Emergency Action Level Flowpath 3.

Fission Product Barrier Status Indications PEP-101, Rev. 2/1 Page Ba of 12

0 4

ki 0

l 0

t