ML17319B656

Clarifies 810710 & 820407 Submittals Re NUREG-0737,Item II.F.1,Attachment 1, Noble Gas Monitoring & Requests Extension of Time from Implementation Dates for Attachments 1 & 3, High Range Containment Monitor

ML17319B656
Person / Time
Site:	Cook
Issue date:	11/05/1982
From:	Hunter R 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:0705, AEP:NRC:705, NUDOCS 8211120337
Download: ML17319B656 (11)

Text

REGULAT Y INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:82111203 DOC ~ OATEN'2/11/05 NO PRIZED:'O DOCKET ¹ FACIL:50 315 Donald C ~

Cook Nuclear Power Planti,Unit l~ Indiana 8

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Cook Nuclear Power Plant~ 'Unit 2i Indiana L

05000316 AUTH INANE AUTHOR AF F ILIATION HUNTER'S R,S>>

Indiana 8 Michigan Electric Co, REiC IP ~ NAME REC IP IENT RFF ILIATION DKNTONrH ~ R ~

.Offi ce of Nuclear Reactor Regul ationi Dir'ector SUBJECT>> 'Clarifies 810710 8

820407 submittals re NUREG 0737iItem II' F>>liAttachment lr "Noble.Gas Monitor ing" L requests extension of time from implementation dates for Attachements 1

L -3~ "High Range Containment Noni~tor DISTRIBUTION CODE:

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INDIANA II MICHIGAN ELECTRIC COMPANY P. O.

BOX 18 BOWLING GREEN STATION NEW YORK, N. Y. 10004 November 5, 1982 AEP:NRC:0705 Donald C. Cook Nuclear Plant Unit Nos.

1 and 2

.Docket Nos. 50-315 amd 50-316 License Nos.

DPR-58 and DPR-74 NUREG-0737, Item II.F.1 Attachments 1 and 3

Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.'. Nuclear Regulatory Commission Washington, D. C.

20555

Dear Mr. Denton:

This letter serves to clarify our submittals dated July 10, 1981 (AEP:NRC:0586) and April 7, 1982 (AEP:NRC:0578D) with regard to NUREG-0737, Item II.F.1-Attachment 1 ("Noble Gas Monitoring") and to request an extension of time from the implementation dates for Item II.F.1 Attachments 1 and 3 ("High Range Containment Monitor") to which our earli'er letters had committed us.

The first point of clarification concerns the function of the lower containment radiation monitors, tag numbers ERS-1300 and 1400 in Unit No.

1 and ERS-2300 and 2400 in Unit No. 2.

Table 1 of the Attachment to AEP:NRC:0586 identified six sets of radiation monitors being provided in order to fulfillthe requirements of NUREG-0737 Items II.F.l-Attachments 1 and 3.

One of the sets of monitors corresponds to the lower containment radiation monitors.

The first function of these devices is to monitor the containment lower compartment atmosphere during normal plant operation.

The second function of the devices is to monitor post-accident lower compartment radiation levels following decay of the containment pressure.

The ability of the monitors to perform their post>>accident function is physically limited by the five (5) psig pressure limit of the gamma scintillator window on the iodine detector.

At present, procedural control would limit use of the devices to periods of time when containment pressure was less than three (3) psig.

Indiana 6 Michigan Electric Company (I&MECo.) believes that use of these monitors post-accident following the decay of containment pressure is acceptable and consistent with the requirements of NUREG-0737 because of the somewhat redundant functions performed by 8211120337 821105 PDR ADOCK 05000315 P

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NRC:0705 the devices and the unit vent monitor in evaluation of plant effluents and because of the limited period of time when the devices would not be available for post-accident service.

A revised page 1 of Table 1 of the Attachment to AEP:NRC:0586 is attached for your convenience.

The second point of clarification is related to a change in the tag numbers given in Table 1'of the Attachment to AEP:NRC:0578D.

The correct tag numbers for the post-accident high range containment area monitors are VRA-1310 and 1410 for Unit No.

1 and VRA-2310 and 2410 for Unit No. 2.

A revised Table 1 of the Attachment to AEP:NRC:0578D is attached for your convenience.

In our letter dated December 12,

1981, AEP:NRC:0652, ISHECo.

committed to an implementation date for Item II.F.l - Attachments 1 and 3 of thirty days after startup from the 1982 refueling outage for each Unit.

For Unit No.

1 this implementation date would be November 9, 1982.

For reasons detailed below, I&MECo. requests further extension of time to implement the requirements of Item II.F.1 - Attachments 1

and 3 ~

Several problems have been experienced with Radiation Monitoring System (RMS) equipment installed to fulfillthe requirements of Item XI.F.l-Attachment 1.

The specific problems are as follows:

(1)

Externally mounted RMS detectors have been provided to monitor noble gas activity at the main steam safety valves/power operated relief valve on each of the four secondary loops.

The electronic interface boxes for the detectors on loops 2 and 3 in Unit No. 1, tag numbers MRA-1701 and MRA-1702, are experiencing failures due to high temperatures, even though the interface boxes were purchased with a high operating temperature specification, The equipment supplier, Eberline, has been contacted and both IQKCo and Eberline are presently investigating this matter.

Should the temperatures in the vicinity of the two interface boxes be found to be unacceptably high, then the boxes will have to be relocated.

The preliminary estimate for design and physical relocation of the boxes is three weeks.

(2)

The steam jet air ejectors's and gland steam condenser vent monitors are still encountering moisture problems, even after installation of moisture separators and heat tracing.

A redesign or modification of the moisture removal system for these monitors is presently being investigated.

The preliminary estimate for redesign and/or modification is at least six weeks.

Pith regard to Item IX.F.1-Attachment 3, "High Range Containment Monitor", IMKCo. is aware of the interim 10 CFR 50.55(e)

Mr. Harold R.

D on P:NRC:0705

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report submitted by Consumers Power Co. concerning quality program and manufacturing deficiencies affecting radiation monitoring equipment supplied by Victoreen for use at the Midland Nuclear Generating Station.

This matter is currently under investigation by American Electric Power Service Corporation (AEPSC) in accordance with company procedures related to 10 CFR 21 "Defect:/Noncompliance" reporting.

The scheduling uncertainties which we now face and which are, largely, outside our control, prevent us from providing you with a date for completion of.the system.

We anticipate providing you with a new completion date by December 31,

1982, This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned.

Very truly yours,

/os R. S. Hunter Vice President cc:

John E. Dolan - Columbus M. P. Alexich R.

W. Jurgensen W. G. Smith, Jr.

Bridgman R. C. Callen G. Charnoff Joe Williams, Jr.

NRC Resident Inspector at Cook Plant - Bridgman

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REVISED TABLE 1 EQUIPMENT DESCRIPTXQA (AEP:NBC:0586)

Description No. Per Contxol Unit Safety Action Detector Instr.

51 I2 Class Trip/Alarm Type Range BE Isotope Notes ard/or Post Accident High Range Containment Area Monitor 2

2 IE Alarm Ion l P briber 1Q R/HR Photons above 6D KeV (Gross Radia-tion)

Mfg VICIOREEN Model:

877-1 Detecto 876A-1 Readout 879-1 Opt. Isol.

Displays Continuous, Display on Demand CBT Power:

CLASS IE, Train Orien Lower Containm nt Radiation 1nitor (Airborne)

(Off Line)

Note (1) 2 2

NM-IE Trip E Alarm B Scint

+ G.M.

B Scint B Scint 105 to 10 uc/cc 4%{4-pi) eff. 9364keV 6a (4-P~Q eff SrY

)

Noble Ws Iodine Particu-late Mfg: EBERLINE Model: SPING-4 Display: Display on Demand E CIT Power: Supplied by U.P.S.

Unit Vent Effluent Radiation Monitor (Airborne)

(Off Line) 1 1

NON-Tr;ip 6 Alarm same as 52 above Note (1)

Monitoring of Post Accident Conditions inside containment can be initiated only when tlat contaireent pressure decays below'3 psig and the supply and return sanple lines are unisolated

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BRUISED EKXCSURE TO AEP:NRt:0578D NGRKE-0737 SYS.

EQPT.

NAME PLT. ID SYS.

COMP.

EVAL. NGRKET REF.

FRCM AEP Eg.

EEQ NEC:00578B tNOTE 1)

I.D.2 XZ.B.1 IZ.B.3 II.D.3 II.E.1.2 IZ.E.4.2.2 Plt. Sfty Paraneter Diaplay Post Accident-Sampling Valve Position Indication AEW Flm Ind.,

Cont. Isol.

Dependability NSO-21 to 24 NSO-61 to 64 Hone Assigned QR-107 Lmt. Swtchs.

On NRV-151,

152, 153 FFZ 210r220r 230, 240 QCR-301 (Note 2}

Yes Yes Later LS-1 for Limit Switches IZ.F.1.1 IZ.F.1 2 II.F.1. 3 II.F.1.4 Noble Gas Lait.

IocULne iWnit'or Post Accident CT High Range Area Monitor Upper CZ Area Monitor CZ Pressure ERS-1300, 140A No 230Q 8 24QQ P(Note 3g VRS-1500 a 2500 SRA 1800 E 1900 E 2800 E 2900 MRA-1601, 1602,

1701, 1702, MRA 2601'602'70 1E 2702 QR-108 VRA-13M,1410 Yes 2310 6 2410 VRS-1101, 1201 2101,2201 PPP-300 to 303 PPA-310 to 313 Not Required Later I29SI30 (mes 4)

Hot RBguired II.F.1.5 CT Ãtr. Level NLA-310 NLZ-311,320 321 Yes IZ.F.1.6 CT Hydrogen I g Revised None Assigned Hot Applicable

(AEP:NEC:0578D)

NUHZG-0737 SYS.

HQPT.

NAME PLT.

ZD EQ. Egg SYS.

COMP.

PVZ. WOBZSHEET REF.

FBGM AEP NBC-'00578B (NOTE 1)

IZ.F.2.1 ZI.F.2.3 XZ.G.1 XI.K.3.1 XX.K.3.5 XI.K.3.12 Subcooling Mtr.

(Pressure Temp. I~ebs)

Level Inst.

Pawer Supplies to PZR Belief Valves Block Valves, and Auto PCEV Xsol.

Auto Tripof KS Pumps Anticipated Trip on Turbine Trip NTR-110 to 140 NXR-210 to 240 NPS-121, 122 NLX-110 to 130 111 to 131 NRV-151 to 153 NMO-151 to 153 NLP-151 to 153 NMO"151,152,153 Not Applicable 128 (NTR's) 122 a 123 (NPS Unit 1) 123 5, 124 (NPS Unit 2)

(NOTE 4)

S11-1 (NRV's)

V9-1 (NMO's and 118 (Unit 1) NLP's 119 (eu.t 2 NLP's)

(HvrE 4).

V9-1 (NOTE 4)

Tb be Later Established N'o Not Recpired e 1 QQy the prirnM~ device System ccnponent Evaluation Nozksheet is listed since the corss-reference listing included in AEP:NBC:0578B provides tb~

correlation of associated items such as cable and termination.

Wte 2 Containnent Xsolation Valves for:

a) b)

c)

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IZ.B.3 HCR 416I 417I 496'97'35 Ec 536'CR 105I 106'09 a 110 Item IZ F 1 1 ECR 31~

32~ 33'5 6 36 Item II.F.1.6: ECR-10 through<<29 inclusive Nate 3 Monitoring of Post Accident Conditions inside containnent can be initiated only gh g

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sample lines are unisolated

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Nate 4 Page nunhers corresponding to our forthcoming suhnittal No. AEP:HRC:0578B fQ Revised

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