ML16340E014
| ML16340E014 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 11/29/1983 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | Parr O, Rosa F, Sheron B Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8312090368 | |
| Download: ML16340E014 (16) | |
Text
Docket Nos.:
50-275 and 50-323 flEflORANDUf< FOR:
Attached List FROfl:
SUBJECT:
George W. Knighton, NRR member Diablo Canyon Allegation Management Program Staff GUIDANCE FOR PREPARATION OF THE DIABLO CANYON ALLEGATIONS EVALUATION Your management has been instructed to prepare-evalua'tio'n'f'or.some 80 allegations and licensing requirements on a first priority basis.
These include the allegations provided each of you and other items shown on the enclosed listings.
Step; 2 refers to Low,Power License and Step 3 refers to Full Power License.
All work products are scheduled to be received by George W. Knighton by COB December, 9, 1983 in order to have the Allegation
December 16, 1983.
The schedule for full power needs will be provided later.
In order to efficiently use the limited '-time available, please work on the IDVP SER (Step 2) input and evaluate all allegations to determine those that are not significant, those that must be evaluated prior to issuing a low power license ai1d those requiring evaluation prior to full power licensing.
Due to the limited time for review.
we propose that your work priorities be as follows:
1 Allegations requiring evaluation to issue a low power license 2
IDVP 8 ITP (Step 2)
SER input 3
Low Power ~License SE input 4
Allegations requiring evaluation prior to issuance of full power license 5
IDVP 8 ITP (Step 3)
SER input 6
Full Power License SE input 7
Allegations requiring evaluation post full power licensing, if any A format for preparation for your final evaluations is being prepared and will be provided to you this week.
The format will permit quick assembly of the SER without retyping 8312090368 831129 PDR ADQCK 05000275 POR
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OFFICEI EQRNAMEI1'ATE 5
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NRG FORM 318 (10-80) NRCM 0240 OFFICIAL RECORD COPY USGPO:
1&81~960
go/ 3g SN If any questions, need for information, or meetings arise contact George II; Knighton or Bart C. Buckley immediately.
Enclosure:
As stated Qrlglnam atgned bV:
G@gga O. KCgMc%
George lt. Knighton, Chief Licensing Branch No.
3 Division of Licensing cc:
R. Hattson R. Vollmer T. Speis D. Eisenhut T. Bishop w/enclosure R. Houston w/enclosure L. Rubinstein w/enclosure D. thuller w/enclosure J. Knight w/enclosure ltt. Johnston w/enclosure F.
Rowsome w/enclosure B. Schierling w/enclosure DISTRIBUTION
<Document=Control=-(-50=275/323:)m NRC PDR PRC System LBI13 Reading GllKnighton HSchierling BBuckley JLee TNovak OFFICE%
SURNAMEI5 DATE Q
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USGPO5 5995~990
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License Itn.,>
! i'/9/03 I.n.i Povier
!'!I.ep 7)
I ull Pnwer
~<Ste 3)
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IDVP Pi ITP SER IDVI'i ITP SER ha'.ural hornn Circ (Pump Trip) T.S.
Emerqency Facil ities I!parade (Amend)
(Si.olley in OELD reviews)
PASS Procedures P,reek< ater T.S.
CCl! T.S.
ihip!;('ndix R
Rel. Guide 1.97 FSAR ul)da te Cnnl.gaol Heavy Loa<!s (Phase II)
Hinh Point-Vents (Generic)
Relief Valve Testing (Generic)
Systems Interaction p!,'i,
~
~ i~(,mls H~ns S./DE Kniqht ISuckley/Chandler I!ans S./OEI D q r~n //f,y
!!a us S./DE Knlql)t
.~!'i 1 son/DS I I!ous ton I!ans S./DSJ lluller I!ans/OEI.D
';!i 1 son/OEI.D Duckley/DE Johnston Buckley/DSI Houston I!ans S/DSI Ruhenstei>>
I!ans/DSI I!ouston Hans/DE Knight Hans/OST I'X><'"
di I ni ):
1>l.//./4I'ull I'ower Lic.
T. S.
Fu':I Power Lic.
Condition Fu'.1 Power Cnnd.
Fu11 Pnwer
~ ic.
Con(!i tion Pr
~ r.r T Full Pov.er I ic.
Condition Full Pov.er Lic.
Chandi tion EGO 1( tt.er
!=ull Pokier L',c.
Condition Full Porn.r Lic.
Condition Full Popover Lic.
Condition Report on acceptahility
TABLE OF ALLEGATION ASS ICiiliiFNTS Al 1 e(ation
~ssicSned Division Branch Su ort Branch 1.
2.
3.
5 6.
7.
e.
9.
10.
11.
12.
13.
14.
15.
16.
17.
18.
19.
20.
21.
22.
23.
24.
25.
26.
Attempted sabotage Explosives/Antinuclear blockage Seismic Ilualification CClJ Single Failure Capability CGA Heat Removal Capability CCW INC Design Classification Seismic Category I/Category II Interface Seismic Design of Diesel Gen.
I t'xh.
USI-17 Systems Interaction Generic Seismic Til ing of Containment Classification of Platform (Category I/Category II)
HELBA did not meet
- FSAR, RG 1.46 Inadequate Seismic Systems Loads on Annulus Structural Steel not Calculated Properly Inadequate Tornado Load Analysis of Turbine Building High Energy Pipe Break Restraint Inadequate NSSS SSE Load Inadequate gA/gC allegations Safeguards
- Sensitive klealth Physics personnel do not meet AtlSI requirements ALARA Program - Paper Tiger Radi ation tlonitors 1 ack sens itive ify In~iimidation of (jC Inspectors HPFol ey NCR '
rejected without good cause.
Deficiency in use of "Red Head" anchors for raceway support Foleyd'clrridocument NCR's issued by field inspectors OI OI NRR
, NRR NRR NRR NP,R NRR NRR NRR NRR NRR NRR l'JRR OI OI Region V
Region Y
Region Y
OI Region V
Region V
Region V
DSI/Pubenstein OS I/Rubens te i n OSI/Pubenstein OS I/llouston OST/Rowsome DE/Knight DST/Schroeder DE/Knight DST/Rubenstein DSI/Rubenstein DSI/Rubenstein DE/Knight DE/Knight De/Knight DE/Knight DE/Knight ASB/Parr ASB/Parr ASB/Parr ICSB/Rosa PRAB/Tha(lani EOB/Noonan GIB/Yniel SGEB/Lear ASB/Parr RSB/Parr ASB/Parr SGEB/Lear SGEB/Lear t'iEB/Bosnak SGEB/Lear ASB/SGEB SGEB SGEB I
t<EB/Bosnak
%lie ation 27.
Welding and QA deficiency in "Super5~rv}
28.
Annulus Structure Reverification Program inadequate 29.
Pipe Restraints Design Inadequate 30.
Inadequate Documentation of Safety Related Equipment 31.
QA Procedures for Struct. Analysis 32.
Seismic Analysis Containment 33.
Turbine Building (Class
- 2) Contains Class 1
/salem~
4 componen.fs 34.
Imcomplete as-built dr gs 35.
Lack o support calcs for fluorescent liqht fixtures 36.
Resolution of Fluorescent Light fixture interaction 37.
Solid State Protection System Relays 38.
PGGE ignoring spurious closure of md;valves 39.
No control R
annunciation of closed RHR suction valve l0.
RHR hot leg suction not single failure 11.
Or g,"inadequate
)2.
License management unresponsive to problems k3.
LicenseeReporting Failure 14.
License Improp. Assessment of Design Change Nof~ce l5.
Design inconsistency in FSRR RllR valves
'6.
HPFoley QA procedures voiding NCR's incorrectly i.7.
Plant P;f>>.
System
.'8.
SI Study and associated Nods
'9.
Emergency Sirens not seismic quuI<4<<"
Assiqned Region V
l'lRR NRR Rr gion V
Region Region V
Region V
l'lRR Region V
Region Y
NRR ISE Division DE/Knight DF/I n'ic~4i DE/Knight De/Knight DE/Knight DF/Knight DE/Knight DE/Knight DE/Knight OS I/Hous ton DSI/Ilouston DSI/Houston OS I/Ilouston OST/Rowsome ranch SGEB/Lear S6 l-'c/Leone ViCA/Bosnak I
FOB/Noonan SGEB/Lear SGEB/I ear SGEB/Lear EQB/Noonan EQB/Noonan ICSB/Rosa ICSB/Rosa RSB/Sharon PSB/Sharon RRAB/Thadani Su
.ort B
a AES/
IE/OAB OS I/AEB SGEB/Lear Region V
RSB/Sharon RSB/Sharon ICSB/Rosa ICSB/Rosa
Alle ation
- 50. 'lant Security should have been retained 51.
Risk of job action to allegers 52.
Construction 8 hrgs in progress after fuel load-inappropriate 53.
'Helder qualification could bepurchased 54.-
Mire traceability not evident0iork by PGKE and Foley,,'5.
Bechtel approved analysis of small bore pipe by altering failed analysis 56.
Pitting of Hain steam and feedwater piping 57.
Foley used uncert and unqualified g.C.
Inspect prior to 1983 58.
Foley allows "Red Head" anchors studs reported improp ly installed 59.
Foley lost cable traceability 60.
Foley purchased material
~rom unapproved vendors
~Assi ned ra ASS OELD OI Region V
HRR NRR Regi,on V
Region V
Region V
Region V
Division DE/Knight DE/Knight Branch YiEB/Bosnak HEB/Bosnak Su ort Branch 61.
62.
63.
64.
66.
67.
68.
Lack of Document control Foley lacks adequate sampling of cable pull activities Foley has lost material tracability through upgrade c ( ri~.>> c los$ 1 6 c Jar 5 2 Grout test sampling based on special tests rather than field t'<sH'oley documents prior to 1980 questioned-no review required prior to 9/1981 license issuance date Defective weld reports rejected by Foley Negligence by PGItE flooding at 55 <+.
elevation pipe tunnel ti"-t: Pullman-Kellog. audit Pegion V
Region Y
Region V
Region V
Region V
Reg on V
Region V
IZE
~
~
~il le ation I9.
Revision of Draft Case Study "C"
'0.
Falsification of response to NRC notice of Violot-',t'gn
'1.
Alledged use and sale of drugs
~~81 08 Ppgqrg~
/1II<qc'cl Selling Crr dVuOS De4 c4ve p)pjgq D(5ckc/'f(fQ plplIiwcj4Mc!os'o gpgyij)p/n)gp
~ @Dl"'ara Spilt J
>=b rc;,
bryan On 7-Beg~
Bcoicl'~J >olj:ot "'.e avail aotv~ anil//jo/
1'0, Encit ooi s ai Cojocll&hN
'-/iC, sos jh iP' '<<>> in vari,e$
oi-sio~io.
C <c~
<<>VnS YC'. 'Yn< erHeyc~evfg VP5$0/jS"P(q>
~ljssirned IAE OI OI Region V
F'~pili~ 'I/
E~t]iGN V Pc c) o~V
\\
Pe.r) ) ~iil/
Pc7cr) (gal 9 k~oc~
>o at/
gogi&n V
'P~~qi on 0 Division
!/
DC Branch VE,S
1 J
NOV 29 ADDRESSEES Olan Parr, Chief Auxiliary Systems Branch Division of Systems Integration Faust
- Rosa, Chief Instrumentation 5 Control Systems Branch Division of Systems Integration Brian Sheron, Chief Reactor Systems Branch Division of Systems Integration Vincent Noonan, Chief Equipment gualification Branch Division of Engineering George Lear, Chief Structural and Geotechnical Engineering Branch Division of Engineering Robert Bosnak, Chief Mechanical Engineering Branch Division of Engineering Ashok'handani, Chief Reliability 5 Risk Assessment Branch Division of Safety Technology
Ph
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