ML20198T175

Supplemental Application for Amend to License NPF-43, Removing Primary Containment Monitoring Sys Valves T50-F406A & T50-F406B from Tech Spec Table 3.6.3-1

ML20198T175
Person / Time
Site:	Fermi
Issue date:	06/07/1986
From:	Agosti F DETROIT EDISON CO.
To:	Adensam E Office of Nuclear Reactor Regulation
References
VP-86-0062, VP-86-62, NUDOCS 8606110356
Download: ML20198T175 (5)

Text

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l June 7, 1986 VP-86-0062 Director of Nuclear Reactor Regulation l Ms. Elinor G. Adensam, Director Project Directorate No. 3 Division of BUR Licensing U. S. Nuclear Regulatory Commission Wa'shington, D.C. 20555

Reference:

1) Fermi 2 URC Docket No. 50-341 MRC License No. NPF-43

2) Detroit Edison Company to NRC Letter

" Request for Amendment for Fermi 2 Technical Specification Table 3.6.3-1",

VP-86-0003, February 4, 1986

Subject:

Supplement to Request for Amendment to Fermi 2 Technical Specification 3.6.3-1 The purpose of this letter is to provide additional information to supplement the original amendment request, Reference 2, as requested by the NRC. On February 4, 1986, Detroit Edison submitted a request for an amendment to the Fermi 2 Technical Specifications which would remove T50-F406A and T50-F406B from Table 3.6.3-1, " Primary Containment Isolation Valves" (Reference 2) . Deletion of valves T50-F406A and T50-F406B from Table 3.6.3-1 will allow the removal of the valves and associated piping from the Primary Containment !!onitoring System (PCMS) .

As discussed with !!r.11. D. Lynch on !!ay 23, Detroit Edison is planning to remove the valves during the current outage. To support the Company's outage schedule, I request this amendment be effective no later tnan July 8, 1986.

8606110356 860607 ol PDR ADOCK 05000341 PDR P , t i

4 Ms. Elinor G. Adensam June 7, 1986 VF-86-0062 Page 2 Configuration The PCMS piping and valve arrangement for containment sample atmosphere flow is illustrated in FSAR Figure 7.6-10. The remote-manual valves T50-F406A and T50-406B are located on containment atmosphere sample lines within the PCMS. The sample line which contains T50-F406A, as well as T50-F051B, penetrates the primary containment through the f-port of penetration number X-48. The sample line which contains T50-F406B penetrates the primary containment through the f-port of penetration number X-27.

The relative location of penetrations X-48 and X-27 is shown in FSAR Figure 3.8-2, " Developed View of the Primary Containment".

Primary containment penetrations X-48 and X-27 are classified as Type 4 and Type 5, respectively. A typical cross-section view of both penetration types is shown in FSAR Figure 3.8-8.

Valve Removal and Line Caps (Attachment 1 and 2)

Subsequent to the removal of valves T50-406A, T50-406B, and T50-F051B, tuo pipe-caps shall be installed that will close-off the respective sample lines. The pipe-cap for the sample line associated with valve F406A shall be welded just inboard of the valve's current position. The pipe-cap for the sample line associated with valve F406B and F051B shall be welded to the f-port of the X-27 penetration.

The f-port of penetration X-27, with a qualified welded cap in place, becomes an integral part of the primary containment boundary and complies with the design criteria use for the drywell, ASME Section III for Class 2 vessels.

The pipe-cap on the sample line running through penetration X-48 complies with the same pipe design standards for piping between the primary containment and the primary containment isolation valves (P34-F403B and P34-F404B).

Ms. Elinor G. Adensam June 7, 1986 VF-86-0062 Page 3 The " caps" used will:

1. Be one-inch socket weld pipe caps, 3000 lb rating, SA182-F304 (Class II) or SA182-F316 (Class I) as available. All work will be performed in accordance with ASME Section III, Subsection NC 1971 through 1971 Winter addendum and ASME Section XI 1980 through 1981 Winter addendum.

2. Meet the requirements of QA Level I and Seismic I.

3. Nondestructive examination requirements shall be per ASME Section III, Subsection NC, Article NC 5000 1971 Edition through Winter 1971 Addenda.

If further discussion is necessary, please contact Mr. R. L. Woolley, (313) 586-4211.

Sincerely,

~~^a-_f? E 'h' Attachments cc: Mr. M. D. Lynch Resident NRC Inspector Supervisor, Advance Planning and Review Section Michigan Public Service Commission USNRC Document Control Desk Washington, D.C. 20555

Attachment 1 )

BEFORE 1

P340074048 V8- 73 75 T5000F406B , ,

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' PCMS PENE7 RATION [V** ISO No. X-27 PORT 5"I- .~ T##00EA0&A

.FSAM TYPE F/&.5# 'PENET' 3.9- B P&NETRA T/0N NO.

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X- 48, FORT "F "

~:~ TYPE 4 PENET #

~ FSAK F/&.# 3. 8-6 l

NOTE:

FSAM f/G. 3. 8-2, DEVELOPED V/EWof THE PR/ MARY CONTAINMENT '

SHOWS THE KELA TIVE LOCATIONOFPENETRATIONS X- 27 ANDX-46 CNTHEPR/MAKy CONTA/NMENT SHELL. .

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Attachment 2 AFTER P340054048 V8 7375 r

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/ \ j L C50 3-7305 50 CAP 'T' .1-g4 -, -,

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PENETRATl0N- .

'No.X-2 PORT "F"

. TYPE 5 T FSAt F/G. # 3.9'-B P&NETRATl0N NO.

X- 48, PORT "F "

7YPE 4 PENET.

FSAK F/&.4 3. 8-8 l

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FSAM f/G. 3. 8-2 s DEVELOPED V/EWCf THE PR/ MARY CON 7AINMENT ",

SHOWS THE KELA TIVE LOCATIONOFMNETRAT/0NS W- 27 ANDX-46 ON THEPK/MAKY CONWNMENT SNELL..

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