ML20079K750

Public Version of Change Sheet 1 to Rev 0 to Emergency Plan Implementing Procedure PMP 2081.EPP.029, Initial Core Damage Assessment

ML20079K750
Person / Time
Site:	Cook
Issue date:	12/22/1983
From:	Townley E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17320A908	List: ML20079K750
References
PMP-2081.EPP.02, PMP-2081.EPP.2, NUDOCS 8401250130
Download: ML20079K750 (8)

Text

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AHP 2030-DCR-001 , I" 4

. . No. 14273&

Date: Dec. 22, 1 DOCUMENT ISSUE RECORD INDIANA & MICHIGAN ELECTRIC COMPANY s

DONALD C. COOK NUCLEAR PLANT ce cooso msmem 3 QUALITY CONTROL DOCUMENT CONTROL - Original 11-1,118-1,11C-1 1 MASTER FILE - Purple 8 OPERATIONS - Green 9 DMINISTRATIVE - Orange 7 .1,7A-1,78 2,.7C.2,TSC-2 5 .1,5B .1,5C-.1,50-6 LIBRARY - Gold 1 PLANNING - Black 2 MAINTENANCE - Blue 4 MANAGERIAL - Brown RLD 19 OTHERS WGS, BAS,ELT,EAS PHJ *SEE BELOW 2 OUALITY ASSURANCE - Red 17 TECHNICAL - Pink 2 - CONSTRUCTION -YELLOW J 14-2 8-1,8A-1,8B-1,8C-1,8D-1, 12-3 8E-7,8F-1,8G-1,8H-3 DOCUMENT DOCUMENT NO. NO.OF DOCUMENT - SUBJECT OR TITLE ORIGINATOR: AND/0R REVISION COPIES ISSUED EMERGENCY PLAN PROCEDURES Initial Core Damage Assessment J. Ersland via PMP 2081 EPP.029 63 Information Records Rev. O, TP# 1 P Center 12-20'-83~

DCR DEC 2 31983 i

Document issue Record Receipt Acknowledgement: COMMENTS AND/0R NOTATIONS:

OTHERS Documents affiliated with this D.I.R. # have been filed in

- . file. Superseded

]

Visitors Center-1 (1 Controlled, documants have beca destrcyed or modified as appicable.

NRC-R-III-1 1Informatio'n) 8401250130 840118 NRC, Wash,0C-1 M. Alexich-1

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hDRADLCK05000 Westin5house-2 R.F. Kroeger-1 XM signature Date A.juda E0F

, RETURN TO: PLANT 00CUMENT CONTROL S. Richardson N

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Ponu ssas INDIANA AND MICHIGAN ELECTRIC COMPANY DONALD C. COOK NUCLEAT. PLANT INSTRUCTION AND PROCEDURE CHANGE SHEET

,  ! INSTRUCTION OR PROCEDURE NO.:PMP 2381.EPP.029 REVISION NO.: O CHANGE SHEET NO.: _L TITLE: INITIAL CORE DAMAGE ASSESSMENT PAGE L of _L i

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ORIGINATED BY: n< _ DATE: /I/603

,, MANAGEMENT STAFF: Cf//rks//lt/M DATE: /2MM3 i SENIORREACTOROPERAT0k: E8  :- DATE: /Z -(- 85 Q.A. SUPERVISOR: , , ((/dMf_ _ , - . DATE: 19 DecAP PNSRC: D D k@NDATE: lx//S/S'a l

PLANT MANAGER: E Mat <.n.8c., DATE: /2 -20W l

P90rmfjog ggc~ 7 . N M OAff / /< b . e EXPIRATION DATE: Life of Revision u

DESCRIPTION OF CHANGE l

Correction of containment sumo samoles for dilutions durino cost accident conditions.

REASON (S) FOR CHANGE l Incoroorate dilution factors involved in P.A.S.S. use.

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INSTRUCTIONS FOR INCORPORATING CHANGE RFPIACF- Paco 1 of 2 (List of Effective Paops). Rev. O with eage 1 of 2. Rev. O. TP-1.

Pace 2 of 2 (List of Effective Paoes), Rev. O with oace 2 of 2. Rev. O. TP-1.

Pace 6 of 10. Rev. O with oace 6 of 10. Rev. O. TP-1.

Ann- Page 6A of 10. Rev. O. TP-1.

EXHIBIT E, Rev. O, TP-1.

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J LIST OF EFFECTIVE PAGES -

.; PAGE NUMBER REVISION NUMBER AND DATE I ,

Page 1 of 10 Revision 0, 5/31/83 Page 2 of 10 Revision 0, 5/31/83

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! Page 3 of 10 Revision 0, 5/31/83 i

. Page 4 of 10 Revision 0, 5/31/83 Page 5 of 10 Revision 0, 5/31/83 Page 6 of 10 Revision 0, TP-1,12-20-83

Page 6A of 10 Revision 0, TP-1,12-20-83 Page 7 of 10 Revision 0, 5/31/83 i -

1 Page,8 of 10 Revision 0, 5/31/63 i

Page 9 of 10 - . Revision 0, 5/31/83 Page 10 of 10 Revision 0,5/31/83 ATTACHMENT 1, Page 1 of 1 Revision 0, 5/31/83 ATTACHMENT 2 Page 1 of 1 Revision 0, 5/31/83 L,

EXHIBIT A Page 1 of 1 '

Revision 0, 5/31/83 EXHIBIT B,

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i. LIST OF EFF.E_CT_IVE PAGES (Cont'd.)

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j FUEL PELLET MELTING MONITOR READING _ SAMPLE DOSE RATE 6

10% 10 R/hr 34 R/hr 6

l- 50% 5 x 10 R/hr' 170 R/hr 7

,. 100% 10 R/hr 340 R/hr 1

4.3 Core damage assessment based on post accident samples j results. Record data on attachments 1 and 2.

4.3.1 Obtain a sample of the reactor coolant in

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- order to investigate the changes in radionuclides concentrations relating to

' the fuel condition.

Using appropriate 12 THP. PAS. procedures, analyze the reactor coolant sample to check for the presence and concentration of krypton, xenon, iodine, cesium and tellurium radionuclides. Use the maximum activities for different fuel failure scenarios to determine the formula to uce in determining percentage of fuel failures as indicated in paragraphs 4.3.2 through 4.3.5.

Samples obtained via the post accident sampling panel are automatically diluted by a factor of 1000. In case further sample dilution is required, the measured radionuclide concentrations should be multiplied by a second dilution factor (DF 1).

DF y=(ht + 1)

' 5- where: w= total weight of diluent material (weight of stable material), i.e. distilled water.

i w1 = total weight of undiluted r material (weight of l

radioactive material).

If the reactor coolant system is incapable of maintaining pressure during a LOCA, use of the PASS for coolant system and/or RHR samples may not be possible. In such an event, samples of the lower containment Page 6 of 10 Rev. O, TP-1

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PMP 2081.EPP.029 volume may be collected via the PASS, and

. sample activity results must be corrected for dilution by use of form 2081.EPP.029 Exhibit E.

, 4.3.2 Assume the maximum cladding failures by arbitrarily attributing all activity released in the reactor coolant for each radionuclide to fuel cladding. failures as follows:

DF ACF = measured radionuclideCF concentration (Ci/q) i l

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INDIANA &kICHIGANF0WERCOMPANY DONALD C. COOK NUCLEAR PLANT

! PLANT MANAGER PROCEDURES

?j i INDEX j4

-) I Identificatiori TIRE

. Cover Sheet Number Rev. & Date Procedure Rev. No.

! PMP 2081 EPP.025 Activation and Operation of Revision 1 -

the Emergency News Source 6-24-82 (ENS) (An Emergency Operations i Facility) '

EPP.026 Use of Stable Iodine for Pevision 1 TP-1, 5-24-83 EXP Nn Thyroid Blocking During a 9-8-82 Radiation Emergency i

EPP.027 Unit Vent Emergency Release Revision 0 TP-1, 4-29-83 EXP Nh Level Determination 3-1~83 l

EPP.029 Initial Core Damage Assessment Revision 0 TP-1, 12-20-83 EXP-i, 5-31-83 L/R -

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