ML17334B605

Clarifies One Fission Product Barrier Threshold Value as Requested by Staff on 961024

ML17334B605
Person / Time
Site:	Cook
Issue date:	10/25/1996
From:	Fitzpatrick E INDIANA MICHIGAN POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
AEP:NRC:1192E, TAC-M89878, TAC-M89879, NUDOCS 9611010307
Download: ML17334B605 (8)

Text

~ CATEGORY+

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9611010307 DOC.DATE: 96/10/25 NOTARIZED: NO DOCKET FACIL;.SQ-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 50-~16 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana M 05000316 AUTH. NAME AUTHOR AFFILIATION FITZPATRICK,E. Indiana Michigan Power Co.

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

SUBJECT:

Clarifies one fission product barrier threshold value as (

requested by staff on 961024.

DISTRIBUTION CODE: R045D TITLE: OR, CORTES RECETVED:LTR Submittal: Emergency Preparedness 3 ENCL 3 SIZE:

Plans, Implement'g Procedures, C NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME G LTTR ENCL ID CODE/NAME LTTR ENCL PD3-3 PD 1 1 HICKMAN,J 1 1 INTERN N98 2 2 NRR/DRPM/PERB 1 1 NUDOCS-ABSTRACT 1 1 EXTERNAL: NOAC 1 1 NRC PDR 1 1 D

0 U

E N

NOTE TO ALL NRIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPZES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 8 ENCL 8

Indiana Michi Power Company heal 500 Circle 0'ive Buchanan, 49107 1395 INDIANA MICHIGAN POWER October 25, 1996 AEP:NRC:1192E Docket Nos.: 50-315 50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Gentlemen:

Donald C. Cook Nuclear Plant Units 1 and 2 PROPOSED EMERGENCY ACTION LEVELS RESPONSE TO REQUEST FOR CLARIFICATION (TAC NOs. M89878 and M89879)

The purpose of this letter is to clarify one fission product barrier threshold value as requested by your staff on October 24, 1996. The "Loss" threshold value for containment barrier 3.4 currently reads, "Primary to secondary leakage greater than technical specification limit AND UNCONTROLLED release of secondary coolant from the associated steam generator is occurring". Your staff proposed, and we agreed to, the following change to that threshold value: "Primary to secondary leakage greater than technical specification limit AND release of secondary coolant from the associated steam generator to the environment is occurring".

Page 4 of 26, revision 2, of PMP 2080 EPP.101, "Emergency Classification", the EAL basis document for containment barrier 3.4 - steam generator secondary side release, and page 12.3-72, revision xx of the emergency plan have been changed and are provided in the attachment to this letter.

We remain available to answer any additional questions that the NRC staff might have.

Sincerely, E. E. Fitzpatrick //

Vice President P QL/Q jen 0g OO+ Attachment ISA

'P6iiOi0307 96i025 PDR ADOCK 050003i5 F PDR

U. S. Nuclear Regulatory Commission AEP:NRC:1192E Page 2 cc: A. A. Blind A. B. Beach MDEQ - DW & RPD NRC Resident Inspector J. R. Padgett

ATTACHMENT TO AEP:NRC:1192E PMP 2080 EPP.101, "Emergency Classification" Page 4 of 26, Revision 2 Donald C. Cook Nuclear Plant Emergency Plan Page 12.3-72, Revision xx EAL Basis Document Containment Barrier 3.4 - Steam Generator Secondary Side Release

PMP 2080 EPP.101 Attachment A FISSION PRODUCT BARRIER REFERENCE TABLE

3. CONTAINMENT BARRIER Applicable Modes: 1,2,3,4 LOSS POTENTlAL LOSS 3.1P Critical Safe Function Status Unisohble breach of containment. Containment Critical Safety Function Status Tree - RED.

4R-Containment pressure/sump level NOT performing 4R-consistent with expected conditions.

4R- 3.2P Containment Pressure Rapid unexplained containment pressure or sump level decrease following pressure increase caused by Hydrogen greater than 4%.

LOCA. 4R-4R- Containment spray systems both inoperable OR fail to auto start on Hl-Hl containment Entry into ECA-1.2, LOCA OUTSIDE CONTAINMENT. pressure.

4R-4R- Both conta~ent air recirculation fans inoperable OR fail to auto start on Hl-Hl contai  !

pressure.

3AL SG Seconds Side Release 4R-Containment pressure exceeds 12 psig.

Primary to secondary leakage rate greater than 4R-technical specihcation limit. Containment hydrogen concentration greater than 0.5% AND key hydrogen control equipment (Containment air recirculation/hydrogen skimmer systems, electric hydrogen recombiners OR 4ND- igniters) inoperable.

Release of secondary coolant from the associated 4R-steam generator to the environment Is occumng.

3.5P Containment Radiation 4R-Containment area radiation greater than 1000 R/hr.

37E ~SEC Jud emenl 4R-Assessment of core damage greater than 20% clad failure.

4R-3.6P Core Exit Thermocou les Core Cooling Critical Safety Function Status Tree - RED.

AND-Restoration procedures are not effective within 15 minutes.

4R-37P S~EC Jud ement Page 4 of 26 Rev. 2

FISSION PRODUCT BARRIER REFERENCE TABLE

3. CONTAINMENT BARRIER Applicable Modes: 1,2,3+

LOSS POTENTIAL LOSS 3.1P Critical Safe Function Status Unisolable breach of containment. Containment Critical Safety Function Status Tree - RED.

4R-Containment pressure/sump level NOT performing 4R-consistent with expected condmons.

4R- 3.2P Containment Pressure Rapid unexplained containment pressure or sump level decrease following pressure increase caused by Hydrogen greater than 4%.

LOCA. 4R-4R- Containrnent spray sYstems both inoperable OR fail to auto start on Hl-Hl containment Entry into ECA-1.2, LOCA OUTSIDE CONTAINMENT. pressure.

4R-4R- Both containment air recirculation fans inoperable OR fail to auto start on HI.HI pressure.

3.4L SG Seconda Side Release 4R-Containment pressure exceeds 12 psig.

Primary to secondary leakage rate greater than 4R-technical speciilcation Emit. Containment hydrogen concentration greater than 0.5% AND key hydrogen rogen con control o equipment (Containment air recirculation/hydrogen sklmmer systems, eiectric hydrogen recomblners OR 4ND- igntters) inoperable.

Release of secondary coolant from the associated 4R-steam generator to the environment Is occurring.

3.5P Containment Radiation 4R-Containment area radiation greater than 1000 R/hr.

E,7E ~SEC Jud emenl 4R-Assessment of core damage greater than 20% clad failure.

4R-3.6P Core Exit Thermocou les Core Cooling Critical Safety Function Status Tree - RED.

4ND-Restoration procedures are not effective within 15 minutes.

4R-E7P ~SEC Jud emenl 12.3-72 Revision xx

DONALD C. COOK NUCLEAR PLANT BASIS FOR EMERGENCY ACTION LEVELS FISSION PRODUCT BARRIERS FISSION PRODUCT BARRIER NAME, LOSS/POTENTIAL LOSS, & DESCRIPTION CONTAINMENTBARRIER 3.4 - STEAM GENERATOR SECONDARY SIDE RELEASE THRESHOLD VALUE LOSS:

Primary to secondary leakage rate greater than technical specification limit AND release of secondary coolant from the associated steam generator to the environment is occurring POTENTIAL LOSS:

None MODE APPLICABILITY 1,2,3,4 BASIS (References)

NORMAL CHARGING hiODE - The normal charging flow path through the volume control system including design and alternate flow paths, and flow to reactor coolant pump seals.

LOSS - Secondary side release paths to the environment include atmospheric relief valves and main steam safety valves, the condenser air ejectors, and the gland seal vent. A release path to the environment should be considered to exist if a main steam FPB 3.4 - SECONDARY SIDE RELEASE

Page 2 safety or an atmospheric relief is failed open. Containment LOSS due to steam releases via the steam jet air ejector and gland seal vent monitors should be declared on the basis of dose assessments rather than by direct application of the fission product barrier table. The technical specification limit is one gallon per minute through all steam generators or 500 gallons per day through any one steam generator.

For smaller breaks, not exceeding the capacity of one charging pump in the NORMAL CHARGING MODE, an ALERT classification will result if the ruptured steam generator is isolated. If the steam generator remains unisolated, this EAL will be a discriminator for SITE AREA AND GENERAL EMERGENCIES.

POTENTIAL LOSS - None DEVIATION FROM NUMARC: None FPB 3.4 - SECONDARY SIDE RELEASE