ML17334B605
| 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
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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.
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 CORTES RECETVED:LTR 3 ENCL 3 SIZE:
TITLE: OR, Submittal:
- Plans, Implement'g Procedures, C
NOTES:
RECIPIENT ID CODE/NAME PD3-3 PD INTERN N98 NUDOCS-ABSTRACT EXTERNAL: NOAC COPIES LTTR ENCL 1
1 2
2 1
1 1
1 RECIPIENT ID CODE/NAME HICKMAN,J NRR/DRPM/PERB NRC PDR COPIES LTTR ENCL 1
1 1
1 1
1 G
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 500 Circle 0'ive
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 jen 0g OO+
Attachment ISA
'P6iiOi0307 96i025 PDR ADOCK 050003i5 F
PDR P QL/Q //
U. S. Nuclear Regulatory Commission Page 2
AEP:NRC:1192E 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
FISSION PRODUCT BARRIER REFERENCE TABLE PMP 2080 EPP.101 Attachment A LOSS
- 3. CONTAINMENTBARRIER Applicable Modes:
1,2,3,4 POTENTlAL LOSS 3.1P Critical Safe Function Status Unisohble breach of containment.
4R-Containment pressure/sump level NOT performing consistent with expected conditions.
4R-Rapid unexplained containment pressure or sump level decrease following pressure increase caused by LOCA.
4R-Entry into ECA-1.2, LOCA OUTSIDE CONTAINMENT.
4R-3AL SG Seconds Side Release Primary to secondary leakage rate greater than technical specihcation limit.
4ND-3.2P Containment Critical Safety Function Status Tree - RED.
4R-Containment Pressure Hydrogen greater than 4%.
4R-Containment spray systems both inoperable OR fail to auto start on Hl-Hl containment pressure.
4R-Both conta~ent air recirculation fans inoperable OR fail to auto start on Hl-Hl contai pressure.
4R-Containment pressure exceeds 12 psig.
4R-Containment hydrogen concentration greater than 0.5% AND key hydrogen control equipment (Containment air recirculation/hydrogen skimmer systems, electric hydrogen recombiners OR igniters) inoperable.
Release of secondary coolant from the associated steam generator to the environment Is occumng.
3.5P Containment Radiation 4R-37E
~SEC Jud emenl 4R-Containment area radiation greater than 1000 R/hr.
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. CONTAINMENTBARRIER Applicable Modes:
1,2,3+
LOSS POTENTIAL LOSS Unisolable breach of containment.
4R-Containment pressure/sump level NOT performing consistent with expected condmons.
4R-Rapid unexplained containment pressure or sump level decrease following pressure increase caused by LOCA.
4R-Entry into ECA-1.2, LOCA OUTSIDE CONTAINMENT.
4R-3.4L SG Seconda Side Release Primary to secondary leakage rate greater than technical speciilcation Emit.
4ND-3.1P Critical Safe Function Status Containment Critical Safety Function Status Tree - RED.
4R-3.2P Containment Pressure Hydrogen greater than 4%.
4R-Containrnent spray sYstems both inoperable OR fail to auto start on Hl-Hl containment pressure.
4R-Both containment air recirculation fans inoperable OR fail to auto start on HI.HI pressure.
4R-Containment pressure exceeds 12 psig.
4R-Containment hydrogen concentration greater than 0.5% AND key hydrogen control rogen con o equipment (Containment air recirculation/hydrogen sklmmer systems, eiectric hydrogen recomblners OR igntters) inoperable.
Release of secondary coolant from the associated steam generator to the environment Is occurring.
3.5P Containment Radiation 4R-E,7E
~SEC Jud emenl 4R-Containment area radiation greater than 1000 R/hr.
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.
~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 limitAND 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 ifthe 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 DEVIATIONFROM NUMARC: None FPB 3.4 - SECONDARY SIDE RELEASE