ML17326B229
| ML17326B229 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 05/20/1986 |
| From: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.1, TASK-TM AEP:NRC:0678T, AEP:NRC:678T, NUDOCS 8605280113 | |
| Download: ML17326B229 (8) | |
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~i' REGULA~V INFORMATION DISTR IBUTI~>SYSTEM'i (R IDS) i,'CCESSION NBR: 8605280113 DOC. DATE: 86/05/20 NOTARIZED:
NO DOCKET FACIL: 50-315 Donald C.
Cook Nuclear Power Plant>
Unit 1>
Ind iana 5
05000315 50-3}6 Donald C.
Cook Nuclear Power Plant>
Unit 2>
Indiana 5
05000316 AUTH. NANE AUTHOR AFFILIATION ALEXICH>N. P.
Indiana 8r Nichigan Electric Co.
RECIP. NANE RECIPIENT AFFILIATION DENTON. H. R.
Office of Nuclear Reactor Regulation>
Director (post 851125
SUBJECT:
Requests concurrence w/encl gustification re location of noble gas effluent monitor for main steam lines> per 860215' tr c onc erni ng NUREQ-0737 Item II. F. 1-1.
DISTRIBUTION CODE:
A046D COPIES RECEIVED: LTR ENCL SIZE:
TITLE:
OR Submittal:
TNI Action Plan Rgmt NUREQ-0737 Zc NUREG-0660 NOTES:
REC IPIENT ID CODE/NANE PWR-A ADTS PWR-A EICSB PWR-A PD4 PD 0}
PWR-A PSB INTERNAL: ADN/LFI'1B IE/DEPER DIR 33 NRR BWR ADTS NRR PWR-A ADTS BHJDHFT Q F 04 COPIES LTTR ENCL 1
2 2
5 5
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RECIPIENT ID CODE/NANE PWR-A EB PWR-A FOB WIQQINQTON> D PWR-A RSB ELD/HDS3 IE/DEPER/EPB NRR PAULSON> W.
NRR PWR-B ADTS NRR/DSRO ENRIT RQN3 COP IES LTTR ENCL 1
1 1
1 1
1 0
3 3
1 1
1 1
1 EXTERNAL: 24X NRC PDR 02 1
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LPDR NSIC 03 05 TOTAL NUNBER OF COPIES REQUIRED:
LTTR 32 ENCL 30
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INDIANA8 MICHIGAN ELECTRIC COMPANY IP.O, BOX 16631 COLUMBUS, OHIO 43216 May 20, 1986 AEP:NRC:0678T Donald C.
Cook Nuclear Plant Unit Nos.
1 and 2
Docket Nos.
50-315 and 50-316 License Nos.
DPR-58 and DPR-74 LOCATION OF MAIN STEAM NOBLE GAS EFFLUENT MONITORS NUREG-0737, SECTION II.F.l-l Mr. Harold R. Denton, Director Office of Nuclear Regulatory Regulation U.
S. Nuclear Regulatory Commission Washington, D.
C.
20555
Dear Mr. Denton:
Per Item II of our letter AEP:NRC:0678S, dated February 19,
- 1986, attached is justification for the location of the noble gas effluent monitor for the main steam lines.
As explained in the attachment to this letter, the justification for the location is based on three factors:
space and temperature constraints with placing the monitor on the main steam pipes, the design setpoints of the power-operated relief valves (PORVs) and the safety relief valves, and the preplanned alternative method of monitoring if the PORVs or noble gas monitors are unavailable.
Included in this justification is a discussion of the environmental qualification of the monitors.
We are requesting NRC concurrence with our placement of the noble gas monitors on the PORV discharge line and with our interpretation that this location meets the intent of NUREG-0737, II.F.1, Attachment l.
This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to insure its accuracy and completeness prior to signature by the undersigned.
Very 'truly yours, MPA/pm Attachment M. P.
exich Vice President) 1 cc:
John E. Dolan W.
G. Smith, Jr.
- Bridgman R.
C. Callen G. Bruchmann G. Charnoff NRC Resident Inspector
- Bridgman 86p528p1 1p Bgpp2p PDR ADOCK 050003l5 P
FOR Roe~
ATTACHMENT TO AEP:NRC:0678T JUSTIFICATION FOR LOCATION OF THE MAIN STEAM LINE NOBLE GAS MONITORS At the D.
C.
Cook Plant the main steam line noble gas monitors are mounted upstream of the power-operated relief valve (PORV) on the PORV discharge line.
The space available on the main steam line is insufficient to mount the noble gas monitors directly on this line.
In addition, the temperature of the main steam line is greater than 180 F, which is the temperature limit for the noble gas monitor.
Since the monitor is located upstream of the PORV, the PORV must open for the monitor to be available.
The D.
C.
Cook Plant's PORVs and PORVs throughout the country, have proven to be reliable.
In addition, the design setpoint of the PORVs is less than those for the safety valves.
The PORVs are set at 1055 psig.
The first two safety valves of each loop are set at 1065 psig.
The second two are set at 1075 psig, and the fifth safety valve is set at 1085 psig.
The uncertainties of the setpoints are such that the actual liftpoints may be different from the setpoints, but it is expected that with a pressure transient high enough to open the valves, all the valves would open at the same time.
- Thus, the uncertainties of the setpoints are insignificant compared to the size of the pressure spike.
If a safety valve opens and the PORV does not open or the PORV monitor itself fails, an alternative method to determine the effluent concentration or a default concentration would be used.
A preplanned alternative to determine the radioactive main steam effluents is already in place when offsite power is available.
This method involves'ending a worker to the condenser to obtain a hand-held monitor reading.
This reading is then related to a secondary-side radioactivity concentration.
The doses in the turbine building are expected to be low for all accidents, so access to the area is not a problem.
- Moreover, an alternative method to determine radioactive release concentrations without offsite power available is being developed.
With a loss of offsite power, the main steam isolation valves close.
When these valves are closed the concentration at the condenser is not representative of the secondary-side concentration exhausted out of the PORVs or the safety valves.
Therefore, a second alternative method is being developed.
The alternative method will be based on primary coolant concentrations.
These concentrations will be determined using the post-accident sampling system, which is accessible.
Default values which have been calculated can be used if the PORV monitor is unavailable until concentration estimates are available from the alternative method.
The only environmental qualification concern is temperature, because radiation and steam will not affect the monitor for the types of accidents during which the monitor is needed.
The temperature limit of the detector is 0
180 F.
An analysis of the temperature transient showed that after 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> the highest temperature would be 171 F, but this assumes the safety valves are relieving for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The FSAR assumes the release lasts for only 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
Over that time the peak temperature is 162 F.
We expect the PORV monitor to 0
be available even after the most severe temperature transients.
If the monitor should fail because of temperature, the above alternative method could be used.
Attachment to AEP:NRC:0678T Page 2
The placement of the radiation monitor on the PORV line rather than the main steam line was made because of the heat and space limitations.
At the present location, the monitor determines the amount of radioactivity released through the PORV and consequently the safety valves.
The reliability and the design setpoints are such that the PORV will open before or with the safety valves.
If the PORV does not open or the monitor does not operate, alternative methods will be used to determine the quantity of the radioactive releases.
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$986 DOCKET NO(S). 50-315/316 Hr. John Dolan, Vice President Indiana and IMchigan Electric Company c/o American E'lectric PovIer Service Corporation 1 Riverside Plaza
- Columbus, Ohio 43215
SUBJECT:
D. C. Cook Uuclear Plant, Units 1 and 2
- a. g~,
'DISTR]
ION:
Docket i-ile
-NRC PBk Loca1 PDR PRC System NSIC PllR84 Rdg NDuncan Dlligginton BJYOungblood Rdg OELD The following documents concerning our review of the subject facility are transmitted for your information.
O Notice of Receipt of Application, dated O Draft/Final Environmental Statment, dated O Notice of Availabilityof Draft/Final Environmental Statement, dated O Safety Evaluation Report, or Supplement No.
, dated O Notice of Hearing on Application for Construction Permit, dated O Notice of Consideration of Issuance of Facility Operating License, dated Hi-Wpaklv Dg Mi55MQ Notice; Applications and Amendments to Operating Licenses Involving no Significant Hazards Considerations, dated Ih (See pages 16929 and 16936)
O Application and Safety Analysts Report, Volume O Amendment No.
to Application/SAR dated O Construction Permit No. CPPR-O Facility Operating License No.
, Amendment No.
, Amendment No.
dated
, dated O Order Extending Construction Completion Date, dated O Other (Specify)
Enclosures:
As stated Office of Nuclear Reactor Regulation cc:
See next page OFF1CS~
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