NRC-89-0239, Responds to Generic Ltr 89-21, Request for Info Re Status of Implementation of USI Requirements
| ML19332D221 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| 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) | |
Text
I
'n B. Ralph SyW j
Senior veca President 1
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,f 0430 North Dinee Highamy l
l Neoport, Mich* Dan 481(4 1
(313) bs6 4150
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i' f
P 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 i
If you have any questions, please conta:t Mr. Girija Shukla at (313) 586-4270.
Sincerely, Enclosure cc:
A. B. Davis R. W. Defayette W. G. Bogers J. F. Stang 2}t s
k r
8911300176 891120 ADOCK0500g1
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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 NUMBER
' TITLE' REF.' DOCUMENT APPLICA81LITV' STATUS /DATE*-
REGARMS-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.
A-2/
Asymmetric Blowdown.
NA MPA D-10 Loads on Reactor Primary
.GL.84-04 GDC ;
Coolant Systems-A-3 Westinghouse Steam NUREG-0844 W-PWR, MA Generator Tube Integrity SECY 86-97
'GL 85-02 (No requ%rements)
A-4 CE Steam Generator Tube NUREG-0844 SECV 86-97 CE-PWR NA Integely
.SECV 88-272 GL 85-02 (No requirements) 5 A-5 8&W Steam Generator NUREG-0844 SECV 86-97 S&W-PWR NA Tube Integrity SECV 88-272 GL 85-02 (No requirements)
E A-6 Mark I Containment NUREG-0408 werk'I-BWR C 7/81 SER 3. 8.1.
Shor t-Term Program A-7/
Mark I Long-Term NUREG-0661 Mark I-BWR C 9/87
.NRC letters dated.3/3/97
& 3/12/87 D-01 Program NUREG-0661 Suppl. 1 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 Fermi 2 Updated Safety Analysis Report UFSAR 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 I
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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.
NRC-89-0140 dated 6/15/09.
Without Scrams 10 CFR 50.62-(Hardware.
.NRC 1et ter dated - 10/10/89-Modifications).
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.
+
A-12 Fracture Toughness of:
NUREG-0577 Rev. 1 PWR NA Steam Generator and SRP Revision Reactor Coofael Pump 5.3.4 4
Supports A-17 Systems Interactions Ltre Devoung to.
All_
NC
- Resolved via GL 89'18.
.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.
.Detrott Edison Letter LPA B-60 1E Safety-Related SRP 3.11 Equipment 10 CFR 50.49
--VP-86-0149 dated.
'GL.84-24 12-12-86: _
.UFSAR 3.11.5 Closed by NRC.
Inspectton Reports IR 89-26 (10/19/89)
IR 87-39 (12/8/87)
A-26/
Reactor Vessel Pressure.
. DOS Letters to.
PWR NA WPA B-04 Transtent Protect ion :
Licensees 8/76 NUREG-0224 NUREG-0371 SRP 5.2 GL 88-11 w,
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REF. DOCUMENT.
APPLICABILITV STATUS /DATE*
w %EWARMS.
C Nuw8ER T1TLE
'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" A-36/
Control.of Heavy toads' Nt' REG-0612 A11 C 1/87;
. Detroit Edison letter. -
-C-15 GL 81-07. GL183-42..
-WP-NO-87-0001-C-10 Near Spent Fuel' SRP 9.1.5 dated 1/30/87.
-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
'V' A-40 Seismic Design SRP Revisices. NUREG/ -
All
. t8C.
SRP being revised.
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 A-43 Containment Emergency NUREG-0510..
Ali
.NC No actions required-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)
A-45 Shutdown Decay Heat SECY 88-260 All E 4/92 Witt be resolved Removal Requirements NUREG-1289
'as a part of GL 88-20 NUREG/Cta-5230 on IPE Detroit
.SECV 88-260 Edison letter (No requirements)
NRC-89-0213 dated-10/25/89-
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TITLE
.: REF. ' OOCUnpENT -
' APPLICA9It.1 TV ?
STATUS /DATE*
- REteARMSI
'LO 1C 3/85-SSER 5/ 3.10'
~
4-46?
-Seisetc QualifScotton-
,NUREG-1030l
. Al1 Detroit Edison: letter-
"of Equipment in
-NUREG-1211/.
-deted 11/20/84 Operating Plants
...GL'87-02.:GL 87-03
'A-47 Safety Impl4 cation-NUREG-1217..NOREG-'-
All-E:3/90..
lGL 89-19 response-Juilt be submitted-A of Control. Systems-
- 1218
-by 3/19/90"
, 7- :
'GL 89-19 i
A-48 Hydrogen Controis
'10 CFR 50.44-
' All. encept-C 3/85 -
'SER 6.2.6
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198easures and Effects.
SECV 89-122 PtfRs with
< Detroit-Edison?fetterL
' of Hydrogen Burns Iarge dry-'
9/12/77 on Safety Equipment containments f
.-A-69 Pressurtzed Thermal.
RGs 1.154 1.99.
' PasR MA Shock SECV.82-465 s,
-'d SECY 81-687
-10 CFR 50.61/
GL 88-11 N
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