NRC-89-0239, Responds to Generic Ltr 89-21, Request for Info Re Status of Implementation of USI Requirements.

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Responds to Generic Ltr 89-21, Request for Info Re Status of Implementation of USI Requirements.
ML19332D221
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 11/20/1989
From: Sylvia B
DETROIT EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
CON-NRC-89-0239, CON-NRC-89-239, TASK-***, TASK-OR GL-89-21, NUDOCS 8911300176
Download: ML19332D221 (5)


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'n B. Ralph SyW j

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Ncr/enber 20, 1989 NIC-89-0239 l i

U. S. Nuclear Regulatory Ccunmission -

Attn Document Control Desk '

Washington, D. C. 20555

References:

1) Fermi 2 NIC Docket No. 50-341 NIC License No. NPF-43
2) NIC Generic letter No. 89-21," Request for I Information Concerning Status of Inplementation ,

of Unresolved Safety Issue (USI) Requirenents," ,

dated October 19, 1989 ,

Subject:

Besponse to NIC Generic I.etter 89-21

'this letter is to provide Detroit Fdison's response to NIC Generic letter 89-21 (Reference 2) which was received on October 20, 1989.

The Generic Ietter 89-21 requested us to provide status of inplementation of unresolved safety issues for which a final technical resolution has been achieved and which are applicable to Fermi 2. Our f response to Generic Ietter 89-21 is provided in the enclosed table as requested.  ;

l If you have any questions, please conta:t Mr. Girija Shukla at (313) i 586-4270.

Sincerely, ,

Enclosure cc: A. B. Davis R. W. Defayette

  • W. G. Bogers J. F. Stang 2}t s

k r 8911300176 891120

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FERMI 2 STATUS OF IMPLEMENTATION OF UNRESOLVED SAFETY ISSUES FOR WHICH A FINAL' TECHNICAL RESOLUTION MAS BEEN ACHIEVED 2 -

, .USI/MPA APPLICA81LITV' STATUS /DATE*- REGARMS-NUMBER ' TITLE' REF.' DOCUMENT A-1 water Hammer SECY 84-119 A11 NC UFSAR 6.3.2.12 and NUREG-0927. Rev. 1 .6.3.2.2.5.

NUREG-0993. Rev t- SER 3.9.2 NUREG-0737 Item SER !.A.2.3 1.A.2.3 (p. 22-12)

SRP revistons.

NUREG-0609 PWR - NA A-2/ Asymmetric Blowdown.

MPA D-10 Loads on Reactor Primary .GL.84-04 GDC ; Coolant Systems-NUREG-0844 W-PWR, MA A-3 Westinghouse Steam Generator Tube Integrity SECY 86-97

'GL 85-02 (No requ%rements)

NUREG-0844 SECV 86-97 CE-PWR NA A-4 CE Steam Generator Tube Integely .SECV 88-272 GL 85-02 (No requirements) 5 NUREG-0844 SECV 86-97 S&W-PWR NA A-5 8&W Steam Generator Tube Integrity SECV 88-272 GL 85-02 (No requirements)

E NUREG-0408 werk'I-BWR C 7/81 SER 3 . 8 .1.

A-6 Mark I Containment Shor t-Term Program Mark I Long-Term NUREG-0661 Mark I-BWR C 9/87 .NRC letters dated.3/3/97 A-7/ Suppl. 1 & 3/12/87 D-01 Program NUREG-0661 Detroit Edison. letters GL 79-57 -4/27/87 & 9/11/87.

SSER 5. Section 3.8.1 eC - COMPLETE NC - NO CHANGES NECESSARY NA - NOT APPLICABLE

! - INCOMPLETE E - EVALUATING ACTIONS REQUIRED UFSAR
  • Fermi 2 Updated Safety Analysis Report 32" - NUREG-0798 Feret 2. Safety Evaluation Report SSER Supplement to SER 3/05 - Co # eted prior to issuance of Fermi 2 i Operat R.0 License in March 1985

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USI/MPA NUwSER TITLE REF. DOCUMENT APPLICA81LITY- -STATUS /DATE* 'REWARMS- .

~A-8 mark II Containment _ NUREG-0808 Mark II-9wR NA ."

MUREG-0487 Suppl. 1/2 NUREG-0802. .

SRP 6.2.1.1C GDC 16 ~

A-9 Anticipated Transients NOREG-0460. Vol.'4 All 'I 12/89 Detroit Edison letter.

Without Scrams 10 CFR 50.62- (Hardware . .

NRC-89-0140 dated 6/15/09.

Modifications). .NRC 1et ter dated - 10/10/89-A-10/ ~ BWR Feedwater Nozzle NUREG-0619 swr C 3/85 - Detroit Edison letter CPA B-25 -Cracking Letter f rom DG Eisenhut '6/4/81 SER 3.9.3 and-dated 11/13/B0 4.6.2 GL 81-11' UFSAR 5.2.1.20 a

A-11 Rea: tor Vessel waterial- MUREG-C744 Rev. 1 All C 9/81 SER 5.2.5 Toughness 10 CFR 50.60/ SSER.8/5.2.!'

B2-26 SSER 5/5.2.1 .. ..

UFSAR 5.2.4 and Tables 5.2-7'thru 10.

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Fracture Toughness of: NUREG-0577 Rev. 1 PWR NA A-12 Steam Generator and SRP Revision Reactor Coofael Pump 5.3.4 4 -

Supports Systems Interactions Ltre Devoung to. All_ NC - Resolved via GL 89'18.

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.ticensees - 9/72 "No actions reQu9 red NUREG*1174 NUREG-1229. NUREG/CR-3922 NUREG-CR-4261. NUREG/

CR-4470. GL 89-18 (No reoutrements)

A-24/ Qualification of Class NUREG-OS98. Rev. 1 A11 C 11/05 SSERS. Section 3.11.6.

1E Safety-Related SRP 3.11 .Detrott Edison Letter LPA B-60 --VP-86-0149 dated.

Equipment 10 CFR 50.49 GL 82-09 'GL.84-24 12-12-86: _

GL 85-15 .UFSAR 3.11.5 Closed by NRC.

. Inspectton Reports IR 89-26 (10/19/89)

IR 87-39 (12/8/87)

. DOS Letters to. PWR NA A-26/ Reactor Vessel Pressure.

WPA B-04 Transtent Protect ion : Licensees 8/76 NUREG-0224 NUREG-0371 SRP 5.2 GL 88-11

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Nuw8ER C T1TLE REF. DOCUMENT. APPLICABILITV STATUS /DATE* w %EWARMS.

- 'n-31 Residual Heat Removal NUREG-0606 'All OLs'After C 7/81 'SER 5.4.2' 'S Shutdown Requirements RG 1.113 .01/79.. UFSAR 5.5.743.2 .

RG 1.139 -

and App. 11A" ,

SRP'5.4.7"

. Detroit Edison letter. -

A-36/ Control.of Heavy toads' Nt' REG-0612 A11 C 1/87; C-10 Near Spent Fuel' SRP 9.1.5 -WP-NO-87-0001-

-C-15 GL 81-07. GL183-42.. -

dated 1/30/87.

GL 85-11 -NRC 1etter dated; _,

Letter from DG- 4/21/87 Eisnhut dated 2 12/22/80-A-39 Determination of SRV NUREG-0802 BwR C 9/87 ~ Resolved as a part -

Pool Dynamic-Loads NUREGs-0763.0783.0002 of.A-7 work I Long; and Pressure Transients NUREG-0661 Term Program:.

SRP 6.2.1.1.C

M SRP being revised. 'V' A-40 Seismic Design SRP Revisices. NUREG/ - All . t8C .

Criteria CR-4776 NUR EG/ CE -0054 No actions-NUREG/CR-3480 NUREG/ required.

CR-1582. NUREG/CR-1161 NUREG-1233. NUREG-4776

~NUREG/CR-3805 NUREG/CR-5347 NUREG/CR-3509 a-42/ Pipe Cracks in Boiling ^ NOREG-0313. Rev. 1- swr C 11/89 Det rolt ' Edison Let ter :

wpa B-05 Water Reactors NUREG-0313. Rev. 2 NRC-89-Ot06 GL 81-032 GL 88-01 dated S/12/89 Ali .NC No actions required-A-43 Containment Emergency NUREG-0510..

Sump Performance NUREG-0869. Rev. 1 NUREG-0897. R.G. 1.82 (Rev.-0).~SRP 6.2.2 GL 85-22 No re:3uirements A-44 Station Blackout RG 1.155' A11 E (Awaiting NRC Detroit Ed(son tetter.

NUREG-1032 acceptance of NRC-89-0061 NUREG-1109 DECO. response. dated 4/17/89 ~

10 CFR 50.63 Implementation wtil be completed within one year after NRC acceptance)

Shutdown Decay Heat SECY 88-260 All E 4/92 Witt be resolved A-45 'as a part of GL 88-20 Removal Requirements NUREG-1289 NUREG/Cta-5230 on IPE Detroit -

.SECV 88-260 Edison letter (No requirements) NRC-89-0213 dated-10/25/89-

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A-48 198easures and Effects. SECV 89-122 PtfRs with < Detroit-Edison?fetterL

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9/12/77 on Safety Equipment containments RGs 1.154 1.99. ' PasR MA

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