ML20009A169
| ML20009A169 | |
| Person / Time | |
|---|---|
| Site: | Waterford |
| Issue date: | 06/19/1981 |
| From: | Miraglia F Office of Nuclear Reactor Regulation |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8107090114 | |
| Download: ML20009A169 (12) | |
Text
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t JUN 191981
)
FOTE T0:
Harold R. Denton N
1 THRU:
Darrell G. Eisenhut JUN 2 3198l Robert L. Tedesco u4 ac FROM:
Frank J. Miraglia y
s
SUBJECT:
STATUS OF WATERFORD 3 SER N:
The following branches have provided input which is complete:
Auxiliary Systens Branch fiechanical Engineering Branch Geosciences Branch Utility Finance Branch Operator Licensing Branch The followina branches have provided SER input which is complete but includes onen iters that must ba addressed in a later supplement:
Human Factors Engiacering Branch Environmental Qualification Branch Accident Evaluation Branch Licensee Qualification Branch ETSB uy complete their review with no open issues by June 19. St uctural Engineering Branch may either close issues or deternine that they are confirmatory by June 22. Radiological Assessment Branch may also be able to close all their open itens by June 19, providing we receive the necessary information by June 15.
The attached status sheet provides schedules for closing open items.
I have also attached a list of LP&L's commitments for providing infornation as well as the status of the submittals. For each iten where the information has been received, I have identified the responsible review branch.
It is to be noted that even if we did close out many of the open items for the ACRS, there are two vital areas that cannot be closed out until perhaps late surmrer or fall. These are 1) the overall matter of ranagerent as to organization, training and staffing adequacy and 2) site related natters such as nearby transpor-tation and military f acilities and routes. Without these itens better defined it is not clear how we could complete the review for the ACRS meeting in August.
We are awaiting information fron the applicant.
- SEE PREVIOUS CONCURRENCE.
Frank J. fifraalia. Actino Chief orric r >
DL:LB#3" DL:LB#3*
D-Licensing Branch No. 3 DL:DIR*
. Division of Licens4nt" co mus) ~'SBlack FJMiraglia Te sco
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PDR ADOCK 05000302 PR e uwo im_m m N R C FO R M S............
OFFICIAL. RECORD COPY
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!!OTE TO:
larold R. Denton Tl!RU:
Da ell G. Eisenhut Rob t L. Tedesco FROM:
Frank liiraglia
SUBJECT:
STATUS OF lATERFORD 3 SE3 The following branches eprovided1[putwhichiscomplete:
Auxiliary Systems Branch Mechanical Engineering' ranc Geosciences Branch Utility Finance Branch Operator Licensing Branch /
The following branches have ovid SER input which is complete but includes openitemsthatnustbeadfessedin later supplement:
!!uman Factors Engin ring Branch \\'
Environmental Oual ication Branch Accident Evaluati Branch Lict.see Oualifi tion Branch ETSB may complete t. ir review with no open isstics by June 19. Structural Engineering Branch ay either close issues or dettrnine that they are confirmatory by June 22. Radi ogical Assessment Branch may alhp be able to close all their open itens by Ju 19, providing we receive the nechy ary information by June 15.
The attached atus sheet provides schedules for closing open items.
I have also attache. a list of LPAL's comitments for providing information as well as the stat of the submittals.
For each item where the nfornation has been
- received, have identified the responsible review branch.
Frank J. lif raglia, Acting C ef Licensing Branch No. 3 Division of Licensing DISTRIBUTION:
Docket File 50=382 SIC FJMiraglia SBlack LPDR pk ERA DGEisenhut PDR vW _ B#3 Files RLTedesco 4
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NRC FORM 318itO'80t NRCM O240 OFFICIAL RECOFsD COPY
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UieiiED 5TATES j
NUCLE AR REGlii ATORY CGTATAi33iOT4 l g}'s, g {
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p JUN 1 e 1981 NOTE T0:
Harold R. Denton f
THRU:
Darrell G. Eisenhut Robert L. Tedesco FROM:
Frank J. Miraglia l
SUBJECT:
STATUS OF WATERFORD 3 SER i
The following branches have provided input which is complete:
Auxiliary Systems Branch Mechanical Engineering. Branch Geosciences Branch Utility Finance Branch Operator Licensing Branch The following branches have provided SER input which is complete but includes open items that must be addressed in a later wpplement:
i Human Factors Engineering Branch Environmental Qualification Branch Accident Evaluation Branch Licensee Qualification Branch ETSB may complete their review with no open issues by June 19.
Structural Engineering Branch may either close issues or determine that they are confirmatory by June 22. Radiological Assessment Branch may also be able to close all their open items by June 19, providing we receive the necessary information by June 15.
l The attached status sheet provides schedules for closing open items.
I have also attached a list of LP&L's commitments for providing information as well as the status of the submittals.
For each item where the information has been rect "ed, I have identified the responsible review branch.
It is to be noted that even if we did close out many of the open items for the 1
ACRS, there are two vital areas that cannot be closed out until perhaps late sumer or iali. These are 1) the overall matter of management as to organization, training and staffing adequacy and 2) site related matters such as nearby transpor-tation and military facilities and routes. Without these items better defined it is not clear how we could complete the review for the ACRS meeting in August.
We are awaiting information from the applicant.
1
-(,
y Frank J. Miraglia, Acting Chief l
Licensing Branch No. 3 i
Division of Licensing l
Information Received As of June 4 As of June 12 i
4 MTEB 1 HGEB 5 ICSB 7 ICSB f
6 ICSB 8 ICSB 9 ICSB 13 ICSB i
10 ICSB 16 ICSB 16 ICSB 22 ICSB 19 ICSB 32 CSS 21 ICSB 36 CSB 33 CSB 47 KTEB 35 CSB 48 SEB 37 CSB 50 CPB 39 CSB 55 CPB 40 CSB 69 ETSB 41 CSB 70 EISB 45 MTEB 71 ETSB 51 CPB 72 ETSB 53 CPB 74 ETSB 68 ETSB 75 ETSB 73 ETSB 81 RSB 79 RSB 88 RSB 4
82 RSB B4 RSB 89 RSB 90 RSB 91 RSB 92 RSB 93 CSB
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6/19/81
!i OPEN ISSUES SER STATUS.
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APPLICANT /STAL NON-TMI ISSUES _
BRANCH REVIEWER
..., t c:;
stem and Subsystem SEB Rinaldi Se sni{c CD 1(conf) 6/15 6[
CD 1(confl 6/17 6/
Steel Containment CD 1(conf} 6/15 6f Foundations CD 1
6/1,2 61 Flood Design Considerations liGEB Gonzales S
2 6/5 6
Turbine Missiles MTEB Schiffgens
~
. Reactor Coolant Pressure Boundary CD 2
lium Pre. service Inspection PSI of Class 2 & 3 Components CD 1
CD 1
6/12 Reactor Vessel' Materials.
Elliott Pressure-Temperature Limtis' CD' 1
9/81 6
CD I
6/12 Reactor Vessel Integrity
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6/19/81 0
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BRANCH REVIEWER NON-TM1 ISSUES _
SER STATUS _
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APPLICANT /STAF MTEB Gleim Turbine Disc Integrity S
1 6/1f CAB ;3 Spraul Q List Review CD 1
6/1 EQB T. Y. Cheng Seismic Qualification of Seismic Category I Mechanical &
Electrical Equipment CD 1
7/30 10f DiBenedetto Environmental Design of
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Mechanical & Electrical Equipment CD 1
10/81 114 CEB W i t't -
Organic Materials CD 1
6/12 6/1 Fire Protection System (Safe Shutdown)CD 1
7/31 9/
Sears aAB Block Rad. Protection
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CD 1
6/12 6/
Exclusion Area Control; O
1 5/28 6/1 Campe SAB Nearby. Industrial, Transporta-tion & Military Facilitics/
Routes CD -A 1
Site Proximity Missiles CD -R 1
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APPLICANT /STA1 RSS Rubin /Liang (79) Sizing of Safety Valvos (5.2.2) 0 (80) SDCS Initiation using Safety Grade Equip. (5.4.7) 0 6/30 (81) Shutdown w/o leaving control room (cccumulator isolation valve is locked open) 0 6/12 l
(84) Alarms for Boron Dilution Event (15.2.4.4) 0 6/
(85) Operation of more than one 1
charging pump during boron dilution event- (15.2.4.4) 0 1
Containment sump test-vortex 0
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RCP Shaft break (15.2.3.2) 0 8/82 I
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(86)RCPShaftseizureassuming Loss of AC and T.S. limit SGT leakage (15.2.3.2) 0 8/7 (89) Justify CESEC or use acceptable model for events involving voiding (15.3) 0 7/24
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(90) FW Line Breaks (CESSAR vs Waterford) (15.3.2) 0 8/31 (91) Loss of A/C or tripping RCP's I
during MSL Break Event (15.3.1) 0 7/24 (92) Fuel damage is caused by stuck open A.D.V. vs. no fuel damage for SL Break (15.2.1) 0 7/24 1
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BRANCH REVIEWER NON-TMI ISSUES SER STATUS ti0.
APPLICANT / STAFF I&CSB Rosenthal (15) RPS (Shaft Break)
CD,
f 6/19 6/26 "dconhoII 6/ 2 (11kb80-ystems Required for Safe Shutdown (79-27, and Monitoring CD 2
7/31 8/15 Safe Shutdown)
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Safety-Related Display l
Instrumentation (R.G.1.47)
S 1
6/12 (16) Other Instrumentation Required for Safety (Cont. Vacuum relief syst) 5 1
5/30 6/12 (17) Control Systems Not Required for Safety (Single failure control CD I
N/S study)
II.D.3 CD 1
6/19 6/26 II.F.2 CD 1
6/19 Emergency Diesel Engine Pipi'ng C'D 1
6/12 6/1.9 FSB g
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line 1
Purge Valve closure 1
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APPLICANT / STAR CD 1
6/30 CP3 howers Swellir.g & Rupture I
Rod Bow (1)L*:C.
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liolor.ich Rod Bow 1
6/l(
.- ly l
DNBR Limit 1
1 I
Fuel Power Peaking Analysis 1
6/12 i
CPC 1
i LQ3 Bt:nedict Management & Technical Support.
ll/8f Organization CD
' Operating Organization I
Qualifications of NucTear Plant Personnel Training CD
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Operational Review CD
,l TMI Items CD l
G '. B Andersoa Appendix r.
CD l
CD 20 N/5 Parrotti
- Emergency Plains
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6/12 6/1 6
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APPLICANT / STAFF I
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