ML19332C805

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Forwards Completed Tabulation of USIs for Facility.Most of USIs Do Not Apply to TMI-2 in Current Shutdown Condition. If Decision Is Made to Restart Plant,Issues Will Be Reviewed for Applicability
ML19332C805
Person / Time
Site: Crane 
Issue date: 11/09/1989
From: Roche M
GENERAL PUBLIC UTILITIES CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
TASK-***, TASK-OR 4410-89-L-0118, 4410-89-L-118, GL-89-21, NUDOCS 8911290020
Download: ML19332C805 (5)
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OPU Nuclear Corporation i

Nuclear

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Middletown, Pennsylvania 17057-0191 6'

717 944-7621:

TELEX 84 2386 Writer's Direct Dial Number:-

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(717) 940-8400

, November 9,1989 L

4410-89-L-0118/0440P '

X US Nuclear Regulatory Commission Washington,!DC-J20555 Attention: -Document Control Desk t.

Three Mile. Island Nuclear Station, Unit 2 (TMI-2)

Operating License No. DPR-73 Docket No. 50-320 Response to Generic Letter 89-21

Dear Sirs:

In response' to. Generic Letter 89-21, attached is a completed tabulation of i.

Unresolved Safety Issues (USI) for TMI-2.'

As expected, most of the USIs do cnotiapply to TMI-2 in its current shutdown condition. However, as stated in the attached, if a decision is made to restart the plant, these issues will be reviewed for applicability.

Sincerely,.

Y0[

M. B. Roche Director, TMI-2 ni

'EDS/ emf.

r Attachment cc:

W. -T. Russell - Regional Administrator, Region I J. F. Stolz - Director, Plant Directorate I-4 L. H. Thonus - Project Manager, TMI Site p

.F. I. Young - Senior Resident Inspector, TMI gj it (

0911290020 891109

>PDR ADOCK 05000320 P

PDC GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation

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a J-ENCLOSURE'1 pfg,8 8

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UNRESOLVED SAFETY ISSUES FOR WHICH A FIMAL TECHNICAL RESOLUTION HAS BEEN ACHIEVED'-

USI/MPA NUMBER TITLE REF. DOCUMENT.

. APPLICABILITY' STATUS /DATE*~

REMARKS :

~

-A-1 Water Hasuner SECY 84-119 All-N/A-This issue'will be reviewed NUREG-0927, Rev. 1-for-applicability prior' toJ NUREG-0993. Rev. I restart.

NU2EG-0737 Item

-I.A.2.3 SRP revisions A-2/

Asynenetric R10wdown NUREG-0609 PWR N/A This issue.will be reviewed i

MPA D-10 Loads on Reactor Primary GL 84-04, GDC-4 for applicability prior:toi Coolant Systems' restart. (Ref. NRC letter:

e dated January 30,1985)

.A-3 Westinghouse Steam NUREG-0844-W-PWR N/A Generator Tube Integrity SECY 86 j SECY 88-?72 GL 85-02 (No requfrements) i A-4 CE Steam Generator Tube NUREG-0844.'SECY 86-97 CE-PWR N/A Integrity SECY 88-272 GL 85-02 i

l

'(No' requirements) 4 l

A-5 88W Steam Generator NUREG-0844. SECY 86-97 88W-PWP N/A This issue will be reviewe'd i

Tube Integrity SECY 88-272 for applicability prior to J

Gl. 85-02 restart.

(Ref. NP,C Letter -

l (No Requirements) dated July 17, 1985)

E X-6 Mark I Containment NUREG-0408 Park I-BWR i /A l

Short-Tem Trogres l

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  • C - COMPLETE NC - NO CHANGES NECESSARY I

NA - NOT APPLICABLE-I - INCOMPLETE -

E - EVALUATING ACTIONS REQUIRED M

1

. _ - - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _,. = _

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.EMCLOSURE

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(4410-89-t-0118 - -

Page ' 2 of14 p

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~USI/MPA'

~ NUMBER TTTLE

- REF. DOCt9 TNT APPLICABILITY STATUS /0 ATE *'

REMARKS I

A-7/

Mark I long-Tem NUREG-0661 Mark-I-BWR N/A

i D-01 Program NUREG-0661 Suppl. 1-t GL 79-57 x.

Mark II-BWR' N/A A-8 Mark II Containment NUREG-OR08' Pool Dynamic Loads NUREG-0487, Suppl. 1/2 NUREG-0802-SEP 6.2.1.10 GDC.16-A-9 Anticipated Transients NUREG-0460, Vol. 4 All N/A-

' This issue will be reviewed:

Without Scram 10 CFR 50.62 for applicability prior' to restart.

A-10/

BWR Feedveter Nozzle NUREG-0619 RWR N/A MPA P-25 Cracking Letter from DG Eisenhut dated 11/13/80 GL 81-11 A-11 Reactor vessel Paterial NUREG-0744. Rev. 1 A11 N/A This issue will be reviewed Touchness 10 CFR 50.60/

for applicability prior to 1

82 26 restart. -(Ref. NRC Letter dated February-3, 1983)

A-12 Fracters Toughness of NUREG-0577, Rev. 1 PWR N/A

- This issue will be reviewed Steam Generator araf SRP Revision for applicability prior to~

j Reactor Coolant Pump 5.3.4 restart.

Supports A-17 Systems Interactions Ltr: DeYoung to A11 N/A This issue will be reviewed Itcensees - 9/77 fcr applicability prior. to NUREC-1174, NL9EG-restart.

1229, NUREG/CR-3922, NUREG/CR 8761, NUPEG/.

CR-4470, GL 89-18 l

(No requirements)

A-24/

Ovaliffcation of Class NUREG-0588,.Rev. 1 All N/A TMI-2 is'not required to MPA B-60 1E Safety-Related SRP 3.11' comply with 10 CFR 50.49 l-Equipment 10 CFR 50.49 until 6 months prior to' GL 82-00, GL R4-24 restart.

(Ref. NRC Letter l

GL 85-15 dated ' July 22,1982) 1 m

3 ? -' -

ENCLOSUREi'

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.4410-89-t-0118i

- Page 3 of14 t[>- a USI/MPA J'".

NUMBER TITLE-REF. DOCUMENT APPLICA8ILITY.-

STATUS /DATE*

REMARKS 1

A-26/-

Reactor Vessel Pressure DOP. Letters to :

PWR

. N/A This issue will te reviewed i

MPA'B-04 Trans'ent Protection Licensees 8/76 for applicability prior to -

4 NUREG-0224 restart:

[

' NURER-0371' i ~

SRP 5.2 l

GL 88-11

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A-31 Residual Heat Removal NUREG-0606 All Ols After-N/A

-This issue will.be reviewed Shutdown Requirements RG 1.113,

.01/79.

for. applicability-prior to !

4 RG 1.139 restart.

6

- SRP 5.4.7 A-36/

Contrel of Heavy Loads NUREG-0612 All C,

A' safety evaluation is..

C-10, Near Spent Fuel SRP 9.1.5

. provided to NRC'for each C-15 GL "8147, GL 83-42,

- major lifting activity GL 85-11 prior.to the lift.

In

- Letter from DG addition,.this will-no Eisenhut dated longer be a concern upon.2 12/22/80 entry into Facility-Mode 2.

A-39 Determination of SRV NUREG-0802 BWR N/A Pool Dynamic Loads NUREGs-0763,0783,0G02 and Pressure Transients NUREG-0661 i

SRP G.2.1.1.C A-40 Seismic Design SPP Revisions NUREG/

All N/A j

Criteria CR-4776. NUREG/CR-0054, NUREC/CR-3480,NUREG/

CR-1592, NUREG/CR-1161, WUREG-1233,'NUREG-4776 j

NUREG/CR-3805

' NUREG/CR-5347-NUREG/CR-3509.

3 A-42/

Pipe Cracks in Boiling NUREG-0313. Rev. 1

.. BWR N/A MPA B-05 Water Reactors.

NUREG-0313. Rev. 2

. - a GL 81-03, GL 88-01 1

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ENCLOSURE 1 2,

4410-89-t-0118E ' Page.'4 6fi4.

1" USI/MPA

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NUMBER TITLE REF. DOCUMENT APPLICA8ItITY

. STATUS /DATE*

REMRRRSi 1

A-43 Con +ainaent Emergency NUREG-0510,

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All

' N/A '-

This' issue will'be reviewed Sump Performance NUREG-0869 Rev. 1 for applicability prior 'to;

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NUREG-0897,'R.G.I.82 restart.

(Ref. ' NRC Letter!

(Rev. 0), SRP 6.2.2

~ dated February 18,.1986)

GL 85-22 No Requirements A-44 Station Blackout RG 1.155 All N/A This-issue will becreviewed NUREG-1032 for applicability prior to NUREG-1100 restart.

10 CFR 50.63 4-45 Shutdown Decay Heat SECY 88-260 All N/A This issue will be reviewed -

Removal Requirements NUREG-1289 for applicability prior: to i

NUREG/CR-5230 restart.

SECY 88-260 (No requirements)

A-46 Seismic Ovalification NUREG-1030 All N/A This issue will be reviewed of Equipuent in NUREG-1211/

for applicability prior' to-Operating Plants GL 87-02, GL 87-03

' restart.

(Ref. NRC Letter dated P.ay 5,1987)

A-47 Safety imp!fcation NUREG-1217, NUREG-All N/A of Control Systems 1218 This issue will be reviewed -

GL 89-19 f r applicability prior-to restart.

A-48 Hydrogen Control 10 CFD 50.44 A11.except N/A This issue will be reviewed Measures and Effects SECY 89-122 PWRs with for applicability prior to-of Hydrogen Burns large dry restart.

en Safety Equipment containments A-49 Pressurized Thermal RGs 1.154, 1.99 PWR

.N/A This issue will'be reviewed Shock SECY 82-465 for applicability prior to SECY R3-288 restart.

(Ref. NRC Letter' i

.SECY 81-687 dated December 30, 1985) 10 CFR 50.61/

GL 88-11 1

...

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