ML19332D717
| ML19332D717 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 11/27/1989 |
| From: | Creel G BALTIMORE GAS & ELECTRIC CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TASK-***, TASK-OR GL-89-21, NUDOCS 8912050152 | |
| Download: ML19332D717 (5) | |
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. GEORGE C. CRELL November 27,1989 ji
, VICE PRESIDENT '
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w U.' S. Nuclear Regulatory Commission 3
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tWashington DC:20555 a
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Document Control Desk.
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SUBJECT:
' Calvert Cliffs l Nuclear Power Plant
'q LM Unit Nos.1 & 2; Docket Nos. 50-317 & 50-318 Status ' of implementation of. Unresolved Safety issues, Response to i
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REFERENCE:
(a) Letter from Mr. J. ' G.- Partlow to All Holders of Operating Licenses '
H 9:
and Construction ~ Permits for Nuclear Power Reactors, dated October 19, 1989, Request for Information Concerning Status of.
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Implementation of Unresolved Safety Issue (USI). Requirements (Generic Letter 89-21)
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. Gentlemen:
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- Enclosed -in - Attachment A' is the -'information you requested m Generic Letter 89-21
- (Reference ' a).' Attachment A is a copy' of Enclosure (1) to Generic Letter 21 to
,b
- which we added information in the columns labeled " STATUS /DATE" and " REMARKS."
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' Should-:you have any further questions regarding this matter, we will be pleased to l
{ discussL them' with you.
l Very truly yours J
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GCC/ WPM / dim i
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D. A.. Brune, Esquire J.' E.
Silberg, Esquire R. A.Capra, NRC S.' A.McNeil, NRC
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NUMBER TITLE
- REF. DOCUMENT'
' APPLICABILITY-
-STATtfS/DATE*
REMARKS:
A-7/
Mark I long-Term
- NUREG-0661 Mark I-BWR NA
.e D-01 Program NUREG-0661. Suppl. 1 GL 79-57 A-8 Mark II Containment NUREG-0808 Mark II-BWR-NA Pool Dynamic l'oads
.NUREG-0487, Suppl. 1/2 NUREG-0802 SPP 6.2.1.1C-GDC 16 I, the diverse scram system is being installed in A-9 Anticipated Transients NUREG-0460 Vol. 4 All lhit 2 during the present refueling outage. -
Without Scram 10 CFR 50.62 startup is' estimated to be 6190.
NA(1)
A-10/
BWR Feedwater Nozzle NUREG-0619 BWp HPA B-25 Cracking Letter from DG Eisenhut dated 11/13/30 GL 81-11 A-11 Reactor Vessel Material NUREG-0744, Rev. 1 All NC, CCNPP.Charpy upper shelf energy is less than 30 ft.lbs.
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Toughness 10 CFR 50.60/
82-26 l
NC(1) l A-12 Fracture Toughness of NUREG-0577, Rev. 1 PWp Steam Generator and SRP Revision Reactor Coolant Pump 5.3.4 Supports NC(1)
A-17 Systems Interactions Ltr:
DeYoung to All licensees - 9/72 NUREG-1174, NUREG-1229, NUREG/CR-3922, NUREG/CR-4261, NUPEG/
CR-4470, GL 89-18 (No requirements).
A-24/
Qualification of Class NUREG-0588, Rev. 1 All C,~ the deadline for equipment qualification e s established by the Mic as 11l30185. we received 1.
MPA B-60 1E Safety-Related SRP 3.11 Equipment 10 CFR 50.49 certain EQ violations and responded in a 7]i2188.
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. hose violations as of 5l22l87 (U1) and 5l29l87. (U2).
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-NUMBER TITLE C
REF. DOCUMENT.
APPLICABILITY-
_. STATUS /DATE*
REMARKS I, we suhnitted a license anenanent request on 1 A-26/
Reactor Vessel Pres'sure-
' DOR Letters-to PWR 10/27/89 in response to a 88-11. we egect MPA B-04 Transient Protection Lictnsees 8/76--
- the rec t review our request such that we can NUREG-0224 neet the schedule in a 88-11.
NUREG-0371 SRP 5.2 1
GL 88-11 A-31 Residual Heat Remove 1 NUREG-0606 All Ols After m(l)
Shutdown Requirements RG 1.113,.
01/79.
Control of Heavy Loads NUREG-0612 All
- c, rec issued a safety evaluation report on C-10, Near Spent Fuel SRP 9.1.5 5/27/83 doctsmenting closure of Phase 1.
We-C-15 GL 81-07, GL.83-42, submitted our response to Phase 2 on 3/1/82.
GL 85-11 closure of Phase 2 was doctnerred in a 85-11.
Letter from DG Eisenhut dated
.12/22/80 A-39 Determination of SRV
' Nt! REG-080?..
BWR Pool Dynamic loads NUREGs-0763,0783,0802 and Pressure Transients NUREG-0661 SRP 6.2.1.1.C I, fl u ele p rtical ta h w il k evaluated A-40 Seismic Design SRP Revisio:is, MUREG/
All I" "# N
- t a 87-02, m1 m. see Criteria CR-4776, NUREG/CR-0054, 5I #*
NUREG/CR-3420, NUREG/'
CR-1582, NUREG/CR-1161, NUREG-1233, NUREG-4776-NUREG/CR-3805 NUREG/CR-5347 NUREG/CR-3509 A-42/
Pipe Cracks in Boiling NUREG-0313, Rev. 1 BWR
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MPA B-05 Water Reactors MUREG-0313, Rev. 2 l
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REF. DOCUMENT-APPLICABILITY STATUS /DATE*
REMARKS
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A-43 Containment E rgency-NUREG-0510 All NC
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Sump Perfonnance NUREG-0869 Rev. 1 NUREG-0897, R.G.I.82 (Rev. 0), SRP 6.2.2 GL 85-22 ho Requirements All I, nodifications and procedure changes will be' A-44 Station Blackout RG 1.155 f!
NUREG-1032 coupleted within 5 years after verification by -
NUREG-1109 Director NRR. 'Ihesearedescribedinour6l14f89 10 CFR 50.63 response to 10 CFR 50.63.
I A-45 Shutdown Decay Heat SECY 88-260 All I, to be evaluated as part of our response to Removal Requirements NUREG-1289 a 88-20.' we estimate subnitting our smary NUREG/CR-5230 reportin8l92.
5ECY 88-260 (No requirements)
A-46 Seismic Qualification NUREG-1030 All I, by letter dated 10l7l88 we reported our plans t C "pke plant walkdowns on both Units by of Equipment in NUREG-1211/
Operating Plants GL 87-02, GL 87-03 Sprig 1 M.
A-47 Safety Implication NUREG-1217, NUREG-All of Control Systems 1218 E, we plan to respond to a 88-19 by 3l17l90.
GL 89-19 A-48 Hydrogen Control 10 CFR 50.44 All, except g(1)
Measures and Effects SECY 89-122 PWRs with of Hydrogen Burns large dry on Safetv Equipment containments i
c sa ty eva on rt ed 2l 7
A-49 Pressurized Thermal RGs 1.154, 1.99 PWR 9
Shock SECY 82-465 rule,10 CFR 50.61. ' we continue to track the I
SECY 83-288 accalated fluence for the limiting beltline SECY 81-687 noterials.
10 CFR 50.61/
GL 88.11
.