NRC-87-0175, Application for Amend to License NPF-43,deleting Four Circuits from Tech Spec 3/4.8.4.1, Electrical Equipment Protective Devices,Ac Circuits Inside Primary Containment. Fee Paid

Application for Amend to License NPF-43,deleting Four Circuits from Tech Spec 3/4.8.4.1, Electrical Equipment Protective Devices,Ac Circuits Inside Primary Containment. Fee Paid

ML20235H903
Person / Time
Site:	Fermi
Issue date:	09/25/1987
From:	Sylvia B DETROIT EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20235H905	List: ML20235H918 NRC-87-0175, Application for Amend to License NPF-43,deleting Four Circuits from Tech Spec 3/4.8.4.1, Electrical Equipment Protective Devices,Ac Circuits Inside Primary Containment. Fee Paid
References
CON-NRC-87-0175, CON-NRC-87-175 NUDOCS 8710010208
Download: ML20235H903 (11)

Text

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• B. R:1ph Sylvb Group Vico Frensderit De_tr.oi..t -- , s.

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Septenber 25, 1987 15C-87-0175 U. S. Nuclear Regulatory Commission  ;

Attn: Docunent Control Desk Washington, D. C. 20555 l

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Reference:

Fermi 2 <

NIC Docket No. 50-341  !

IGC License No. IPF-43 l

Subject:

Proposed Technical Specification

(License Anendnent) Change - A.C. Circuits Inside Primary Containment (3/4.8.42 )

I Pursuant to 1(CFR50.90, Detroit DSison Conpany hereby proposes to j anend Operating License IFF-43 for the Fermi 2 plant by incorporating j the enclosed changes into Technical Specification 3/4.8.4.1 A .C .

Circuits Inside Primary Containment. The proposed change is an j a3ministrative removal of four (4) circuits which currently function '

as spare circuits that do not enter prinary containment or connect to containment electrical penetrations.

1 Detroit Edison has evaluated the proposed Technical Specifications against the criteria of 10CFR50.59 an3.1(CFR50.92 anS determined that no unreviewed safety question or significant hazards consideration is

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j involved.

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The Ferir.1 2 Onsite Review Organization has approved and the Nuclear ,

Safety Review Group has reviewed these proposed 'Itchnical l Specification changes arrl concurs with the erclosed determinations. '

Pursuant to 1(CFR170.12(c), enclosed with this anendnent is a check for one hundred fifty dollars ($150.00) .

In accordance with 1(CFR50.91, Detroit DSison has provided a copy of this letter to the State of Michigan.

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0710010200 870925 PDR ADOCK 05000341 g 0g h v 1T \v/)k h

P PM $

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USNIC Septenber 25, 1987 150-87-0175 Page 2 t

if you have any questions, please contact Mr. John E. Price at (313) i 586-4513. .j Sincerely, l

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Enclosure 1 l cc: Mr. A. B. Davis 2 Mr. E. G. Greenman Mr..W. G. Bogers Mr. J. J. Stefano i

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USIUC Septenber 25, 1987

- 13C-87-0175 Page 3 I, B. FALPH SYLVIA, do hereby affirm that the foregoing statements:are based on facts and circumstances' which are true and accurate to the

'best of my knowledge and belief.

aA B. IMLPfl SYLVfA Group Vice President on this MK day of h en_luA; . 1967, before me personally appeared B. Ralph Sylvia, being first duly sworn and says that he executed the foregoing as his free act and deed..

KAREN M. REED Notary Public, Mccrae County, Mkh.

My Commistica Expires Maf__14,193)

Notary Public l

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EECLOSURE LVCEilWD/DIfCUSS13 The Limiting Condition of Operation 3.8.4.1 - A.C. Circuits Inside Primary Containment, currently requires several a.c. circuits inside primary containment to be de-energized during plant Operational Conditions 1, 2 and 3 except during entry into the drywell. The proposed change would administratively remove Item (c) - Circuit Nunber 5 in panel H11-P907B, Item (d) - Circuit Number 4 in panel H21-P552, Item (e) - Circuit Number 1 in panel Hil-P901, and Item (f)

, - Circuit Number 1 in panel Hil-P906C. These four (4) circuits currently function as spare circuits which do not enter primary containment or connect to containment electrical penetrations. These l circuits were changed as spares in June 1985 and the respective loads transferred to circuits which are not required to be listed in the Technical Specifications.

l The Technical Specification 3.8.4.1 lists non-class lE circuits primarily for lighting, utility outlets and convenient power plugs used in the event of plant walkdowns, maintenance and in-situ test and/or observations. These circuits are de-energized in Operational Conditions 1, 2 and 3 except when personnel are entering the drywell.

l The bases of the Technical Specification requirements is to ensure containment integrity by protecting the electrical penetration essenblies. Electrical penetration assemblies installed as part of l the primary containment structure, requires special consideration should they fail to indefinitely withstand the maxinum current available due to a fault inside containment. Such consideration is specified it the Technical Specifications by either de-energizing the circuit or providing a primary an3 backup overcurrent protection device.

In June 1985, while performing the drywell cloreout checklist in preparation for plant startup, it was recognized that de-energization of the four (4) circuits described above caused a loss of power for devices and equipnent required per existing plant procedures. During the ensuing investigation, loads from three (3) of these circuits were transferred to circuits within the same panels which had adequate containment penetration protection. These loads, as notal below, could thus remain energized.

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. Enclosure to NIC-87-0175 Page 2' Previous SouIra LoMs New' Source Item (c) ' Circuit 5, StaMby Liquid Control - Circuit 19, Hil-P907B Hil-P907B Testable Check Valve Solenoid and Light

. Circuit

' Item - (d) Circuit 4, ~. Fuel Pool Alarm' ' Circuit 2, H21-P552 H21-P552 Circuits Item (e) Circuit 1, Core Spray-Testable Circuit 2, Hil-P901' Hll-P901 Check Valve solenoid and Light Circuit The penetrations through which the relocated loads pass are presently protected by dual fusing which is an acceptable alternative to '

de-energizing the penetration circuit. As a result, the new circuit.s were not required to be listed in the Technical Specifications.

Additionally, during the investigation, Item (f) Circuit 1,. Ell-P906C -

was identified containing numerous Reactor Building area rMiation monitors and a drywell radiation monitor horn and sensor. The loMs -

l were transferred to Circuit 17 Hil-P906C ard the Fermi 2 Primary Containment Closecut procedure (PCM 22.000.08) was revised to ensure termination of the drywell radiation monitor horn and removal of sensor upon drywell closure. A copy _of Attachment 5'to PCE 22.000.08, which details the termination of the horn and, removal of the sensor, is provided herein. The removal of drywell equipment and loMs associated with Circuit 17 Hll-P906C is an acceptable alternative to de-energization of the penetration circuit. As a result, the-new.

circuit was not required to be listed in the Technical- Specifications. l The Technical Specification 3.8.4.1, Items (c), (d) , (e) r and (f) are, j therefore, requested to be administratively removed as these four (4)  ;

circuits are presently de-energized spare circuits with no loMs

. connected. As spare positions, these circuits no longer penetratM inside primary containment or affect any penetration assenblies. As they do not connect to penetration assenblies,' they need not be i de-energized in accordance with Technical' Specification 3.8.4.1.  !

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Enclosure to NFC-87-0175 Page 3 STGNIFICMP IWABQS_QQHSlDlWATLW In accordance with 10CFR50.92, Detroit Edison has made a determination that the proposed amendment involves no significant hazards considerations. To make this determination, Detroit FAison must establish that operation in accordance with the proposed amendment would not: 1) involve a significant increase in the probability or consequences of an accident previously evaluated, or 2) create the possibility of a new or different kind of accident from any accident previously evaluated, or, 3) involve a significant reduction in a margin of safety.

l The proposed change to delete Items (c), (d), (e) and (f) from Technical Specification 3.8.4.1 does not involve a significant increase in the probability or consequences of an accident previously evaluated, nor creates the possibility of a new or different kind of accident from any accident previously evaluated, nor involves a significant reduction in a margin of safety. The proposed change deletes four (4) spare circuits which do not enter primary containment a connect to containment electrical penetrations. The circuits were chan9ad as spares and the respective loMs transferred to circuits which are not required to be listed in the Technical Specifications. l The change is an editorial correction only and purely administrative, l and therefore falls into the category of amendments that are j considered not likely to involve Significant Hazards Consideration.

(14870 FR Vol. 48 No. 67 (i)) . This change does not involve a physical change to the plant, change a limiting coMition of operation, or change any operating practice. The removal of these four (4) spare circuits does not change any safety analysis or design  !

basis at Fermi 2. "

MZmottEmL IMPACT Detroit n31 son has reviewed the proposed Technical Specification changes against the criteria of 1(CFR51.22 for environmental i considerations. As shown above, the proposed changes do not involve a significant hazards consideration, nor increase the types and amounts of effluents that may be released offsite, nor significantly increase individual or cumulative occupational raSiation exposures. Based on the foregoing, Detroit Edison concludes that the proposed Technical Specifications do meet the criteria given in 10CFR51.22(c)(9) for a

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Enclosure to NBC-87-0175 '

Page 4 ,

categorical exclusion from the requirement for an Environmental Inpact.

Statement.

CGQUSIQi Based on the evaluations above: '(1) there is reasonable assurance' that the health' and safety 'of the public'will not be' endangered by

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operation :in the proposed manner, and . (2) such activities.will be conducted -in conpliance with-the Commission's1 regulations and proposed amendments will not be inimical to the common defense.'and security or -

.to'the health and. safety of.the public.

l The change. requested herein is. an editorial' correction and purely

' administrative and is like that of Item (1) exanples of amerdments-that are considered not'.likely to -involve' Significant Hazards Consideration (14870 FR Vol. 48 No. 67)'.

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. Enclosure to 10C-87-0175 l

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i CONTAI!NEWP CLOSECUT l l

PROCEDURE INFOINATION a

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POM 22.000.08 (SR)

Anachment 5, Page 1 cf 2 050587 h DISABLING AREA RADIATION MONITOR (ARM) CHANNEL 45 initial /Date Step Number 1.0 Removal of D21-N145 Sensor and D21-SO45A Horn from the Drywell 1.1 On Local Area Radiation Monitor Auxiliary Unit D21-K145 (RB1-B11) Unplug Field Cable 239746-OC (Plug to Auxillary /

Contac 4 from Junction Box H21-P613A). 1

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1.2 Coll Cable 239746-OC around Junction Box H21-P613A and Yellow j Tag in accordance with General Administration j Procedure 12.000.012, " Tagging and Protective Barrier / j System". (

A' 1.3 At Relay Room Panel H11-P884, Process Radiation Monitoring Cabinet, unplug Cable 239754-OK from Sensor J-1 to remove power / 1 from Sensor D21-N145. I

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1.4 Yellow Tag Cable 239754-OK in accordance with General  !

Administrative Procedure 12.000.012, " Tagging and Protective / )

Barrier System *.

1.5 Remove Sensor 021-N145 by unscrewing the Amphenol 0 Connector at the bracket in Drywell at Elevation 640' Azimuth 281.

Alternate Azimuth locations are possible at Elevation 640' at Q Azimuth 2470 or 309 0 /

1.6 Close Door Cover on remote Horn D21-SO45A in Drywell at / I 0

Elevation 640', Azimuth 309 . l 1.7 Give Sensor to Health Physics for storage and /

accountability.

2.0 Disabling Control Room Annunciator i l

input from ARM-45 2.1 At Relay Room Termination Cabinet H11-P863, disable the Hi-Radiation input as follows:

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2.1.1 Install a Jumper between Terminals E-171 and E-173.

1 2.1.2 Document Jumper installation in accordance with General Administrative Procedure 12.000.080,

• Conduct of Electrical /

Field Activities".

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POM 22.000.08 (SR) 'f Attachment _5, Page 2 of 2 1 z

050587 ro a

" DISABLING AREA RADIATION MONITOR (ARM) CHANNEL 45 initial /Date Step Number 2.1.3 Attach interim Alteration Checklist (Attachment 1 of 12.000.080) ,

to the active copy of 22.000.08 located in the Reactor Startup /

l Book in the Control Room.

2.2 At Relay Room Area Radiation Monitor Cabinet H11-P849, disable 1 the Downscale input as follows: .f

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2.2.1 Install a Jumper between Terminals AA-10 and AA-13.

f 2.2.2 Document Jumper installation in accordance with General . .s j Administrative Procedure 12.000.080, " Conduct cf Electrical / 'q Field Activities *. a l

2.2.3 Attach interim Alteration Checklist (Attachment ,1 of 12.000.080) . j to the active copy of 22.000.08 located in the Reactor Startup ' / j Book in the Control Room. f Signatures'(of test personnel) l Printed Names initials 0 _

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Enclosure to I IEC-87-0175 l

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PROPOSED PAGE CINGE EI 1

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