ML20140H428
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| ML20140H428 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 05/15/1985 |
| From: | Linville J NRC |
| To: | Shropshire A NRC |
| Shared Package | |
| ML20138C032 | List: |
| References | |
| FOIA-85-613 NUDOCS 8510220184 | |
| Download: ML20140H428 (60) | |
See also: IR 05000410/1984015
Text
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MAY 151985
MEMORANDUM FOR: Alan Shropshire, Compliance and Investigations Coordinator
FROM: James C. Linville, Chief, RPS 2C, DRP
SUBJECT: CLOSE0VT OF ALLEGATION 84-A-0156, LEAD AUDITOR
CLARIFICATION
The Senior Resident Inspector (SRI) has documented his. re' view of alleged
inadequacies in the certification of Lead QA Auditors in the attached in-
spection report 50-410/84-15. Closecut of the open item 84-15-02 generated in
this report is based on poor documentation of Lead Auditor certification which
had previously been identified by the licensee in QA audit 4 and was documented
in attached inspection report 50-410/85-04 by the SRI. Since the memos which
formed the basis for this allegation were forwarded to the RI anonymously, no
response to the alleger is required.
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WL/ MOHAWK
INTERN AL' CORFf ESPON w ei.o DENCE
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QA844]6S
DisT RICT System ,,9 ..
FROM J, E. Ryan FILE CODE 17.0-Al
EDCiblieF271984-
To A. 5. Kovac - Quality first PrograPATE 'UEA~ '
9MP-2 SUBJECT Quality First Program Reporting Action
Responding to QAP 16.70 of 9/27/84 now on circula
- (which has proven to be a joke around here).
The inf amous Audit No, 4 where the auditors were nearly crucified for We thei
and professionalism by the OA Management started.this scenario in Janu from
conducted an audit of the Nine Mile Point Unit No.3,21984. Ouality
OneAssurance
of our twenty- staff
January 24-27 and continuing from January
~
31 Februaryeicht
18.01, Section 6l1.4 identi-
of tne five met the certification reauirements of OAD
fiec in tne aucit scope.
Eignt r onths later this auditor was assigned tointerim
During this conductQAPa18.01
similar
had audit
been of Nin
Point Urit No.1 Quality Assurance staff. revised and our audit was addr
which had six findings revealed another Lead
1954. Audit No. RG-IN-5Y.N1-84003, All five pf these Unit No.1
Auditor sampling of five to verify for credentials.
Leac Auditors wre deficient in their certifications per AFR r5.
-
Same QA Department, same finding, second NMPC nuclear plant, eight months later, now
revised procedures to MAC standards and all of a second sampling of five Nuclear
Lead Auditors f ail the verification test.
assigned
Significant is the fact that we have an indeterminate number o
Vendor Qualification Surveys... and they may not be cualified themselves to conduct
This non.. nuclear group is not scheduled for
tne survey or sian any documentation!
an internai audit until June 19EE (RG-IN .SY-85007) .
Having this type of ten-for-ten verification history in the negative, places every
Lead Auditor in the Quality Assurance D !partment in question, as well as the recent "O
Under the provisions of QAP 16.70, Rev.
audits / surveys wnich they have conducted.
Section 5.3.5, please. review the significance of this action which may impose a
10CFR-50.55(e) significant deficiency.
m
F.5 /&4e#
J'ohn E. Ryan
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xc: W. B. Williams
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S.R. CORRWOl{ ,,
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DISTRICT System QA841582
FROM J.A. Ferry + .. D "
FILE CODE 3N2.0-M58.26
To QA Departmental Personnel DAT E {0Etobe'r3{~yli4}
SUBJECT Lead Auditor Certification
,
.
,
Lead Auditor qualification is based in part on the involvement
of the indiviaual in five (5) nuclear audits. Many of our
Lead Auditors were so certified based on their participation
in certain surveillances ut Nine Mile Point Units 1 and 2.
I consider this practice.as having been acceptable for the
original certification and for the annual renewals of certif-
'
ication until July 16, 1984, the effective date of issue of
Revision 3 of QAP 18.01.
)
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-J/A. Perry /j
8irector of Q:fality Assurance
JAP /ams
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INTERNAL CORRESPONDENCE
M\. .i.4
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LM G ,- . T. N
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FROM J. E. Ryan
DISTRICT System ..
'
FILE CODE 17 .1)1 - Al
D J. A. Perry
DATE b,.Ttober
- _ _ ~5,7984'
SUBJECT Lead Auditor Certification
Your letter of 10/3/84 (OA841582) has caused a great ceal of
consterr.atior, in the auditing areas of the QAD:
1. li is in direct conflict with your letter of toy it, 1984
(OA840842) to Tony Laratta which in part states. "!ssuance
of Letters or memoranda that conflict or interpret procedures
in sucn a way as to Lessen the QA Procedures recuirements are
not authorized. "
2. It is in conflict with ANSI /ASME N45.2.23-1978, Section 1.4.'3
which in part states,.. ."An audit should not be confused with
surveillance or inspection for the sole purpose of process control
or product acceptance." Niagara Mohawk's both Nuclear facilities
are committed to this standard and no exceptions have been made
inat we are aware.
3. This does not de-fuse the Audit No. 4 or RG-IN SY-N1_84003 Audit
Findings that we had on Lead Auditor Certifications. The concerns
that these findings generated were addressed to your Quality First
Program people on October 2,1984 (OAE44161B) copy enclosed, if you
have not seen it.
Jim I feel that your department wide memo of October 3rd is going to
cause us a great deal of trouble and it should be readdressed, but
this is your action to take.
/ P
(-- qw
John E. Ryan /
JER:19
Attachment
xt: W. E. Williams
W. M. Brvant~
A. D. Laratta - Audit No. /-(Lead)
f
R. R. Consaul - RG-IN-SY-N1.84003 Audit (Lead)
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INTERNAL CORRESPONDENc L,) M Y NIAGARA , - ,,,, - . amon HUMOHAWK FROM J. A. Perry DISTRICT System QA840915
"B"
L C. Beckham DATE June 1, 1984 FILE CODE 17.0-Al
L. Cole
W. Connolly SUBJECT Lead Auditor List
J. Dillon
W. Friedrich
A. Kordalewski
B. Morrison
R. Norrix
0. Palmer
K. Rafferty
A. Spiddle
W. Treadwell
K. Tyger
W. Williams
This memo supersedes memo No. QA840573 issued by D. P. Dise on
April 5, 1984
Based on a recent review of their qualifications, the following persons
are certified as lead auditors in the Quality Assurance Department:
Aiello, Frank Daniels, John Norman, Rudy
Balestra, Bill Diana, Tony Norrix, Bob
Bassett, Tom Dillon, Jim Osypiewski, Frank
Baumler, Charles Doyle, Gerry Palmer, Dave
Bohanske, Tom Ocad, Richard Peceri, Ron
Breigle, Tom Fenton, Roy Sconzert, Perry
Bryant, Walt Kordalewski, Andy Shea, Kevin
Buckley, Jack Kovac, Al Stucky, Larry
Connolly, Bill Laratta, lony Todd, Roger
Consaul, Roger Leskiw, Gary Van Nest, Fred
Cummings, John McDonnell, Mike Wilde, Paul
Dahlin, Roger Murphy, Cecil Winegard, Al
ff n -
p A. Perry
JAP:jan
cc: Lead Auditors Above f
*
J. A. Mitchell { 1 *
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.et ESPO N D EN C E M Y NIAGARA
/- ss oi co
li u MOHAWK
. B. Williams olSTRICT System 04844688
"C"
DATE October 19, 1984 ntE CODE 3 '12'2 J.58.38
W. 8. Bryan:
.
SUBJECT tlR-036 Corrective Action
f
i
The action agreed upon in our meeting with J. Perry to close fir-036 dealing
with possible improper auditor certifications is as follows:
'
W. Williams will take the lead in a certification file review.
'
All records of all currently certified lead auditors will be reviewed
based on the requirements in the QA Program at the time of certi fication.
*
If there are problems noted with any certification, the individual will
be contacted for verification of the problem and any additional i n f orma tio n
which might clear up the problem.
*
The supervisor, at the time of certification of the person whose records
are in question will ' f contacted for any evaluations which may aid in
validation of ouestionable certifications.
'
A list of certified lead auditors who actually acted as lead auditors on
audits since 1981 or supplier pre-quali fication surveys will be Comoiled
and checked for invalid certification.
.
'
Audits or supplier pre-qualification surveys conducted by lead auditors
with invalid certification will be reviewed by a qualified and certified
lead auditor from the Corporate Audit group as well as the Sunervisor of
Corporate Audits. A determination will be made and documented as to
whether the audit can still be considered valid or if a reaudit should be
rescneduled.
*
Prior to refiling any questionable audits or surveys the audit or survey
and the disposition shall be reviewed by the Director of Quality Assurance.
*
In addition, any audits or supplier, pre-qualification surveys since 1981
be certified lead auditors no longer with the company or department will
diso be checked as above including contractor personnel from the same
period.
*
m m 0 4'% BJ
tlo te : QA84447B has been reissued,sfor use as corrective action for tiR 036
with the exception that there will be no new list of lead auditors issued.
If there are any changes to this please let me know. I doubt that we can finish
all this action prior to Jim Dillon transferring the files on tiovember 1,1984
It would be helpful if transfer could be postooned,
'
' ' " a -C . r , u , ,,,,, ,
;
; R E C ElV E ' D_iWesl_ay#B. Williams
f,
d
! i%- 'Supervi'or . Corporate Audits
WRW: Ig
xc: A. D. Laratta N4 M M509AfdCE
J. A. Perry DEPARit.j[tg i
i , ne15-- + . ,
_ m., _, ;.m , . . m..,-... . . . . . . . , . , . , _ . . . - . . _ . . _ . - . -
m.m
INTERNAL CORRESPONDENCE M Y NIAGARA
non n2 aor o sui 4's RuMOHAWl(
FRom J.A. Perry DISTRICT System QA841595
"D"
To QA Departmental Personnel DATE October 5, 1984 FILE CODE 3N2.0-M58.26
SUBJECT Lead Auditor Certification
This memorandum rescinds and cancels my memo of October 3, 1984,
(QA841582) same subject. It was not my intention to deviate
from existing procedures. It appears that the reference memo
could be interpreted as such.
A revision to QAP 18.01 is pending and will address this
issue. Until such time as QAP 18.01 Rev. 4 is issued, the
provisions contained in existing procedure apply.
/
l /
W
A. Perry ()
irector of Quality Assurance
JAP /ams
i I
. me
, - - - -
'
iNTERhAL CCRRESPONDENCE
0- O M Y NIAGARA
, o ,,, , a ., = n4'4u RuMOHAWK
FROM W. M. Bryant DISTRICT System QA844848
"D"
TD :W. D. Baker DATE October 31, 1984 FILE CODE 3-N2.2-M58.48
SUBJECT Response to item #90-84 10/26/84
The items and issues identified in the subject NRC Identified item
aere discussed in a meeting between the NRC Resident Inspectors from
-
NMP-2 and NMP-1, Mr. J. A. Perry and W. M. Bryant on October 25, 1984.
Mssrs. Perry and Bryant indicated to the NRC Residents the corrective
actions already planned regarding the maintenance of certification of
NMPC's lead auditors. The planned corrective actions were as a result
of Nonconformance Report NR-0036 from NMPC QA Audit No. 4. A copy of
the corrective action plan for NR-0036 is attached. When these actions
have been completed, the various concerns about individual lead auditors
; certifications discussed in the October 25th meeting will all have been
i
addressed. Also during the meeting a change to QAP 18.01 was also
discussed.
The target date for the attached corrective action of NR 0036, the issuance
of any change to QAP 18.01 and thus the resolution of this item is
December 1, 1984
/(' hya>&b
W. M. Bryant
Manager - QA Services
i WMB:lg
Attachments
,
xc: C. G. Beckham
J. L. Dillon na
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J. A. Perry ..m..[.5'S['{'ji'lll"3
{.n
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uMOHAWK
rnoM
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. S Williams DistnicT System QAg41996
" C
to W. M. Bryant DATE December 21, 1984 FILE CODE
3-fl2.2.M58.48
SUoJECT Review of lead Auditor Certifications
The certification files for Lead Auditors have been reviewed. This was
initiated due to Nonconfromance Report NR-0036, Audit F inding Peport
AFR-RG-IN-SY-N1-84003-05 and NRC Identified item, NMPC ltem 90-84
of 10/26/84
Several concerns were expressed in the above mentioned reports such as:
instances of inadequate documentation of how experience and education points
were awarced, certifications were not always updated annually, certification
was sometimes prior to completion of five audits, surveillances instead of
audits of ten used as basis for certification. These concerns were all
addressed and corrected during the certification review.
Before reviewing the certifications, the following facts were recognized as being
pertinent to the review and did in fact influerice the determination of validity
of each certification.
*
When many of the lead auditors were first certified, Niagara Mohawk
was committed only to ANSI N45.2.12 Draf t 3 Rev. 4 2/22/74
The requirements in this standard for personnel leading an audit
were only that an auditor be qualified and the the qualification
requirements were to be determined by the auditing organization.
There was no ANSI N45.2.23 which specifies the requirements for
qualification of lead auditors until April 1978.
NRC Inspection Report 50-220/78 11 dated 8 September 19/8 refers
to the inspector having " verified that these Surveillance Reports
and the activities they describe were consistent with AN5! N45.2.12
requi rements for audi ts. . . .". The surveillance reports referred
to were listed in the Inspection Report. This was interpreted by
fijagara Mohawk QA Management as approval to consider surveillances
as audits as long as the content was similar to those reviewed by the
NRC Inspector.
*
hMPC Quality Assurance Procedure QAP 18.10 Rev. 4, Qualification of
Auditors and Lead Auditors was issued to include a " grandfather clause"
allowing surveillances to be used as audits to qualify lead auditors
prior to October 1984 as long as specific criteria were present in the
surveillances. This clause was discussed with the Unit 2 Resident NRC
inspector and agreed to be acceptable for past certifications on
October 25, 1984
,. - . . _ _ _ . . . _ . _
.
.)
, C
__- -- _ - - _ -- - . _ . _ - _ -_. - _ . . - _ . - _ _ _ _ _ _ _
"
! O e 1
.
*
! NMPC Lead Auditors have been certified on several different dates i and to different revisions of the Quality Assurance Procedure 18.01. To j fairly determine if the certifications were valid or invalid one must i look at the requirements stated in the revision of the QAP that was
in force at the time of Certification.
1 I1 ' Other personnel that had been certified as lead auditors that no longer work
for Niagara Mohawk are; M. Henn, G. N. Hodge, J. S. Banges and J. S. tianion.
None of these had questionable certifications. A note was placed in each
of their personnel files stating their auditor certification had been reviewed
i
and were acceptable.
All actions stated in attached letter QA844688 which outlined the corrective i
! actions to be taken to close Nonconfonnance Report NR-036 have been accomplished '
and verified. These actions close out NR-036 and are considered sufficient so
} that the NRC concern Item 90-84 of 10/26/84 may also be presented to the NRC l l 1s ready for their review for closure, j Audit F inding Report AFR RG-IN-SY-N1-84003-05 may also be closed by the above ! actions as soon as training of the lead auditors has been verified. This a
will be done by 12/28/84.
I
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M i h* S/4
,
W. B.f.4flTiams
Supervisor - Corporate Audits j
WBW: 19
!
Enclosure ,
l
xc: J. A. Perry
W. D. Baker
, C. G. Beckham
I
J. C. Dillon l
0. R. Palmer !
F. Laratta !
R. Consaul
L. Zwissler
Audit file
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DEC 2 8 19N
*****
Docket No. 50-410
Niagara Mohawk Power Corporation
ATTN: Mr. William G. Hooten
Executive Director-Nuclear Operations
c/o Miss Catherine Seibert
300 Erie Boulevard West 13202
Syracuse, New York
Gentlemen:
Subject: Inspection No. 50-410/84-15
i
This refers to the routine inspection conducted by Mr. R.A. Gramm Unit 2, Scriba,
of fice on September 10 to November 2,1984 at Nine MiledPoint, to the dis-
d other
New. York of activities authorized by NRC Licens
members of your staff at the conclusion of the inspection.
I
Areas examined during this inspection are described in the NRC Reg
Inspection Report which is enclosed with this letter. Within t t tive
inspection consisted of selective examinations h of procedures and
inspector,
records, interviews with personnel, and observations by t e
Within the scope of this inspection, no violations were observed.
j issued two Notices of Violation regarding deft-
Inspection Report 50-410/84-11 We have received your letter dated to
cient engineering design change control.
October 9,1984 which outlined corrective and preventive actions i
the noted violations. Your letter stated that the corrective action
response to the Notices of Violation were implemente We find that these correc-
f aftsmen to
! the constructor to follow engineering instructions.tive ac
i identify inadequate engineering direction. it appears that, prior
l of inadequate engineering direction previously identified, sed in relationship
to issuance, the impact of the design changes werei not assess were provided
to existing specifications, and that ambiguous l ated todirect onAn int
the installer.
constructors.
that complete and consistent design direction h is prom
i lations
address the rcot cause of inadequate 50-410/84-11.
engincoring review for t e v o
noted within Inspection Report
Except as noted above, no reply to this letter is required. Yo
with us in this matter is appreciated.
,
,
l
I N3/
7
l
f n .. r., nun N va-a,- .. . , r u , .. . u . , e
C
OEC 2 8 1984
,
The responses directed by this letter are not subject to the clearance proce-
dures of the office of Management and Budget as required by the Paperwork
Reduction Act of 1980, PL 96-511.
Sincerely,
W
farry . Ai te r, hlhli
t e fYb s OI
Projects Branch No. 2
Division of Project and Resident Programs
Enclosure: Region I NRC Inspection Report Number 50-410/84-15
cc w/ encl:
Troy B. Conner, Jr. , Esquire
John W. Keib, Esquire
D. Quamme, NMP-2 Project Director
C. Beckham, NMPC QA
NMPC QA
Department of Public Service, State of New York
Public Document Room (POR)
local Pubi tc Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
NRC Resident Inspector
State of New York
bcc w/ encl:
Region ! Docket Room (with concurrences)
Senior Operations Officer (w/o encis)
Chief, Engineering Programs Branch
Section Chief, DPRP
J. Grant, DPRP
W. Cook, DPRP
L. Doerflein, DPRP
State liaison Of ficer (SLO)
E
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.
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4 Allegations
During the inspection period the inspector conducted inspecticns and in-
terviews in response to allegations presented to tne NRC, additionally the
t
t
inspector monitored licensee actions resulting from the presentation of
selected issues to the licensee as noted below:
; a. (RI-84-A-0156) The NRC ttcuived an allegation which stated that QA lead
} auditors had been improperly certified. The allegation also stated
I
i
that improper interpretations had been made regarding the substitu-
* tion of surveillance for audits during the certification process.
The inspecter reviewed the following:
--
ANSI N45.2.23, " Qualification of Quality Assurance Program
.
Audit Personnel for Nuclear Power Plants"
--
ANSI N45.2.10, " Quality Assurance Terms and Definitions"
ANSI N45.2.12, " Requirements for Auditing of Quality
--
Assurance Programs for Nuclear Power Plants"
.
--
Regulatory Guides 1.144 and 1.146
.
' --
FSAR Table 1.8
i
-
l
--
NMPC QAP 18.01 Rev 3, " Qualification of Auditors and Lead
Auditors"
i
l The inspector was informed that two NMPC audits had previously identified
; deficiencies with the lead auditor certification process.
The inspector reviewed NMPC letter QA841582. The letter stated that
surveillances conducted at Units 1 and 2 fulfilled the ANSI requirement
for involvement in quality assurance audits prior to certification as a
; lead auditor. The inspector discussed with the NMPC Director of QA, the
dif ference between a formal audit and surveillance as performed at Unit 2.
l' He then was presented with NMPC letter QA841595 which rescinded the
} guidance promulgated via the earlier letter. Revision 4 of QAP-18.01 has
I
'
since been issued. The QAP currently states that credit can be taken for
surveillance conduct only if the surveillance w15 conducted in the same
fashion as a formal programmatic audit. The current QAP is consistent
with the intent of ANSI N45.2.23.
The inspector reviewed the qualification packages for all current NMPC QA
lead auditors. Numerous concerns were identified, namely:
-annual evaluations performed at greater than 12 month
intervals
-typographical errors
points awarded not substantiated by length of service
-
_.
__
'75'
.
.
,,
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-lead auditor performed his own annual evaluation
,, -one of five audits required for certification performed more
than three years prior to certification
deficient certifications.The licensee was presented with the above c
plan toand
N45.2.23 review
any auditthe lead auditor certifications for complianc
will be evaluated for validity. led by an auditor with an invalid certification
The concerns regarding the lead auditor
certification problems are unresolved pending completion of the NMPC
review.
,
The inspector notes that this issue was originally identified by
the licensee
Report (NR) No.within NMPC QA Audit No. 4 which generated Nonconform
36. The ance
to the extended period of clapsed time since the issuancein
implementation of the corrective action plan. of NR36 to the
(84-15-02).
No violations were identified.
5.
Electrical Raceway and Cable Separation
j
l
req;irements and licensee committmentsepara-
tion: in the ar
--
Regulatory
Systems" Guide 1.75 " Physical Independence of Electric
--
lEEE
and 384-1975, " Criteria for Separation of Class IE Equipment
Circuits"
--
FSAR Sections 1.8 and 8.3
He then reviewed the site procedures and documents that implemented e
t
separation criteria for electrical equipment and provide for QC inspec-
tion:
--
EADCR F01619
--
SWEC Inspection System Handbook
--
Construction Site Instruction (CSI) 9.6, " Documentation
and Control of Cable Separation Conditions and Installation
of Cable and Raceway Separation Barriers"
--
Specification E061A
--
SWEC QA Inspection Plans
between the FSAR description in section 8.3.1.3 He was
and
presented with LOCN 1358 which rectified all but one of the inspector's
.
.
.
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KlNG OF retOSSIA, rt N Nsv L vANt A 3940s
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APR 161985
Docket No. 50-410
Hiagara Mohawk Power Corporation
ATTN: Mr. William G. ilooten
Executive Director-Nuclear Operations
c/o Miss Catherine Seibert
300 Erie Boulevard West ,
Syracuse, New York 13202
Gentlemen:
Subject: Inspection No. 50-410/85-04
This refers to the routine inspection conducted by Mr. R. A. Gramm of this
of fice on February 4 to March 18, 1985 at Nine Mile Point, Unit 2, Scriba, New
York of activities authorized by NRC License No. CPPR-112 and to the discuss-
ions of our findings held by Mr. Gramm wi th Mr. B. Morrison and other members
of your staff at the conclusion of the inspection.
Areas examined during this inspection are described in the NRC Region 1
In;pection Report which is enclosed with this letter. Within these areas, the
inspection consisted of selective examinations of procedures and representative
records, interviews with personnel, and observations by the inspector.
Within the scope of this inspection, no violations were observed.
No reply to this letter is required. Your cooperation with us in this natter
is appreciated.
Sincerely,
f;!).V iL l l)
$.imuel J. Cdllins, Chief
Projects Branch No. 2
Division of Reactnr Projects
Enclosure: Region 1 NRC Inspection Report Number 50-410/85-04
8944MW
.
.
......._........M....._.. . -
Ik
;-
.... , ,
cc w/ encl:
Connor & Wetterhahn
John W. Keib, Esquire
D. Quamme NMP-2 Project Director
C. Beckham, NMPC QA Manager
Department of Public Service, State of New York
Public Document Room (POR)
Local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
NRC Resident Inspector
State of New York
bcc w/ encl:
Region I Docket Room (with concurrences)
Senior Operations Of ficer (w/o encl)
Chief, Engineering Programs Branch
J. Linville, Section Chief DRP
J. Grant, ORP
State Liaison Officer (SLO)
M. Haughey, NRR/ LPM
.
' .
.
_
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.
Es
re-installation and generated Inspection Reports (irs) SSA60392,
SSA60555, 55A60556, and S4C '7376. SWEC conducted training course
#NMF JB QH 0100 on Procedure QS-14.1-NM for personnel associated with
the control of rework activity. No further instances of unauthorized
structural steel beam assembly have been detected by NRC inspection.
This item is closed.
k. (Closed) VIOLATION (84-09-06): Nondestructive examination of elec-
trical penetration assemblies. The penetration assemblies had orig-
t
inally been fabricated by Graver Northeast and the weld surface had
been fully examined by magnetic particle method by that vendor. The
penetration assemblies were turned over to Chicago Bridge and Iron
Co. (C8&I) to complete. CB&I performed radiographic examinations of
the weld, performed the necessary repair ef fort and magnetic particle
examined only the repair area. SWEC N&D's 8428 and 9031 were gener-
ated to document that Chicago Bridge and Iron Co. had not performed a
magnetic particle exar.ination of the entire weld surface but only of
the repair area. The NJE records f rom Graver in conjunction with CB&I
NDE records were reviewed to assure that all required NDE was per-
formed. This item is closed.
1. (Closed) UNRESOLVED ITEM (84-15-02): Certification of NMPC lead
auditors. The licensee reviewed the certification files of all cur-
rent lead auditors and all personnel that had previously acted as
lead auditors. The personnel qualifications were evaluated in rela-
tionship to the certification requirements that were effective at the
time the individual was originally certified. That approach was
necessary because a number of ce tifications took place prior to the
issuance of ANSI N45 2.23 in April 1978. Four lead auditors with
valid certifications were iden t i fied. One individual had not per-
forned in the capacity of lead auditor. The other personnel had l ed
audits at the site and Cherry Hill. The questionable audits were
satisfactoriiy reviewed for compliance with ANSI N45. 2.12 require-
ments. NMPC has issued a new revision to Quality Assurance Procedure
(QAP) 18.10, " Qualification of Auditors and Lead Auditors" to clarify
the certification process, lead auditor records have been amended to
correctly state the basis upon which the individuals were certified.
The licensee stated tha t the untimely resolution of the audit find-
ings relative to the l' sue of auditor certi fications, was caused by
the management re alignments that took place within the QA department
during 1934 Several individuals had been assigned the responsibil-
ity of re.olving this concern, but a lack of continuity existed when
personnel transfers wore af fected. The licensee stated that current
audit findings are closely monitored to assure timely resolution. On
the basis of the review of lead auditor certifications, analysi . of
the questionable audit reports, procedural enhancement, and justi f-
Ication of the time lapso prior to corrective action implementation,
this item is closed.
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INTERNAL CERRESPONDENCE M V NIAGARA !.
.
,oau nn maa 55M 453
H U MM.
!
FROM- W. D. Baker DISTRICT Nine Mile Point #2
Letter #NMP20A105284
T3 Distribution DATE November 7, 1984 FILE CODE 3N2.2-M58.
SUBJECT FORMAL EXIT MEETING 84-15 '
Mr. R. A. Gramm, US NRC Resident Inspector, conducted a formal exit
meeting on Friday, November 2,1984, for the subject inspection which covered
the period f rom September 10 through November 2,1984.
The following personnel were in attendance:
Name Company Position
B. R. Morrison NMPC Mgr. QE
C. G. Beckham NMPC Mgr. QA
G. Griffith NMPC Licensing
J. P. Ptak NMPC Sr. Mgr. Construction
J. White NMPC QA
L. G. Fenton NMPC Auditor
M. J. Ray NMPC Asst. to Proj. Director *
,
R. S. Hyslop NMPC Site Lic. Engineer
S. E. Geier NMPC Nuc. Compliance Verif.
W. D. Baker. NMPC Asst. to Mgr. QA Proj.
C. L. Terry SWEC Project QA Manager
E. Magilley SWEC Asst. Supt.
J. J. Gallagher SWEC SEG-licensing Eng.
R. J. Cuthberson SWEC ESO Principle Eng.
T. L. Baumgartner SWEC Site QA Supervisor
W. C. Taylor SWEC Asst. Supt. FQC
~
I R. A. Granin 0 NRC Resident Inspector
R. Wheeler NRC Resident Inspector
Mr. Gramm opened the exit meeting with the introduction of the newly assigned
resident inspector, Mr. R. M. Wheeler. Mr. Wheeler will assist Mr. Gramm in routine
resident inspections.
period:
The following items were noted by Mr. Gramm as being closed during the inspection
.
79-02-01 (UNR) Graver documentation
.
82-03-05 (OPEN) Risk Release Program
.
82-05-01 (OPEN) HVAC inspection program
.
83-02-02 (OPEN) Cable pull tension monitoring
.
83-05-01 (UNR) Site material ordered without proper QA documentation
.
83-11-02 (UNR) Cable tray fill requirements
.
.
. , , , , . . , . . ~ . ,,
-
. , .
,
. .
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, . , .
_
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89-09-07 (UNR) Lack of spot RT
.
. 84-13-01 (UNR) Allegation involving JCI instrument and tubing supports
78 01 (COR) Graver QA Breakdown
.
. 82 00-01 (CDR) Limitorque Limit ~ Switch ,
f
. 82-00-02 (COR) Emergency Diesel Generator
82 00-11 (COR) PGCC Control Room Equipment
.
N d-
'
The following previously l identified NRC concerns were reviewed L N c m ut'
Gram during the inspection period and have been found to require #J' W * 9,
83-01-07 (UNR) Code required evaluation of NDE require " g4 s
.
. 83-04-01 (UNR) Timeliness of follow-up on NMQA surve4 mn
84-02-05 (UNR) NMPC Corporate Audit Plan
Linear classification of pipe support
.
. 84-11-01 (OPEN)
. 82-00-09 (COR) HPCS qualification documentation
Additionally, the f ollowing items were identified by Mr. Gram:
Unresolved
The inspector performed a general review of NMPC CAR's 84.0046 through 84.0130
/ resulting in two problem areas (11 84-84): .
A.) It has become evident that FSAR comitments , to Regulatory Guides and
standards for example, have not been appropriately translated into site procedures
and specifications.
, B.) Mr. Gram concluded that a review of proposed corrective actions f rom RCI to
NMPC CAR's has shown that the timeliness and adequacy of their responses needs
improvement.
.
E&DCR F01619A proposed an alternate site approach which deviated f rom commitments l
v made in the FSAR. No LOCN was initiated to cover the FSAR deviation prior to the
NRC inquiry. Mr. Gramm has expressed concern with lack of engineering review of
E&DCR's for conformance to the applicable licensing document. (11 82-84) j
.
In reviewing records and hardware for the suppression pool and penetration match
assemblies, Mr. Gram observed that several pieces of hardware were missing (i.e.
pressure gauges, swing bolts). (11 87-84 B, Rev. 1)
.
The NRC inspector noted two copies of IR N2P28380005, located in SWEC's filing
system (ref. Document Transmittal 04-00161). Both IR's contained the same number,
signature, and date, but- included different attributes accepted. Mr. Gram
questions if the IR was improperly amended. (II 87-84 C. Rev. 1)
.
Based upon a review and subsequent concerns with NMPC's Lead Auditor Certification,l
the NRC inspector has concluded that the overall certification program for lead l
/ auditors is not well maintained. (11 90-84)
l.
------.____-_____________,3 __
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-
F0IA REQUEST NUMBER T S~ U ~
DATE hRIGIdATOR PlCIPIENT' nEsrRTPTTON
hSV- NAG AftM4 M mow N K l' toc.4ma (w -er-cC) 'C4KANFAsM
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._ _ _. _ _ . . _ _ _ . .
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Niagara Mohawk Power Corporation
- ATTN: Mr. Gerald K. Rhode
Senior Vice President '
c/o Miss Catherine R. Seibert .
300 Erie Boulevard West ,
Syracuse, New York 13202 .
Gentlemen;
i
;
; Subject: Inspection No. 84-01
This refers to the routine. inspection conducted by Mr. R. A. Gramm of this office
on January 23 to March 2, 1984 at Nine Mile Point, Unit 2, Scriba, New York of
l
activities authorized by NRC License No. CPPR-112 and to the discussions of our
findings held by Mr. R. A. Gramm with Messrs. Morrison, Ray and others of your
i
staff at the conclusion of the inspection.
Areas examined during this- inspection are described in the NRC Region I Inspection .
Report which is enclosed with this letter. Within these areas, the inspection
consisted of selective examinations of procedures and representative records,
interviews with personnel, and observations by the inspector.
'
The Construction Appraisal Team Inspection (50-410/83-18) has previously documented
;
the inability of site audit programs to identify construction deficiencies to
- be a potential enforcement action. During the conduct of this inspection, a
further example of inadequate ITT Grinnell audit effectiveness was identified.
l Your long term corrective actions implemented as a result of the deficiencies
_ .,
identified in Appendix' A, Item 3. of CAT inspection report 50-410/83-18 should -
include resolution of the cause of the deficient conditions identified in
. detail 6. of this report. No written response to this additional finding is'
required at this time.
'
Based on the results of this inspection, it appears that two of your activities
were not conducted in full compliance with NRC requirements, as set forth in
the Notice of Violation, enclosed herewith as Appendix A. These violations have
~
been categorized by severity level in accordance with the NRC Enforcement Policy
(10 CFR 2, Appendix C) published in the Federal Register Notice (47 FR 9987)
~
,
dated March 9,1982. You are required.to respond to this letter and in preparing
i your response, you should follow the instructions in Appendix A.
In accordance with 10 CFR 2.790(a), a copy of this letter cnd the enclosures
.
will be placed in the MRC Public Document Room unless you notify this office,
'
by telephone, within ten days of the date of this letter and submit written
application to withhold information contained therein within thirty days of the
date of this letter. Such application must be consistent with the requirdments
e of 2.790(b)(1). The telephone notification of.your intent to request with-
holding, or any request for an extension of the 10 day. period which you believe
, 'necessary, should be made to the Supervisor, Files, Mail and Records, USNRC
~*
Region I, at (215) 337-5223.
, V
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} .jping = v: -- % v' ~ ~~ Xppeuus >< a
NOTICE OF VIOLATION
Niagara Mohawk Power Corporation Docket No. 50-410
Nine Mile Point, Unit 2 License No. CPPR-112
As a result of the inspection conducted on January 23 - March 2,1984, and in
accordance with the NRC Enforcement Policy (10 CFR 2, Appendix C) published in
the Federal Register on March 9,1982 (47 FR 9987), the following violations
were identified:
1. 10 CFR 50, Appendix B, Criterion X and the Nine Mile Point, Unit 2 PSAR
require that inspection be provided to assure the conformance of field
installations to design drawings and procedures. ITT Grinnell procedures
FQC-4.1-3-9 and FQC-4.2-14-9 require pipe support installations to be
inspected to verify welding and mechanical attributes.
Contrary to the above, as of February 27, 1984, the following ITT
Grinnell final accepted pipe supports; BZ-19EA-3,. BZ-19PN-3, BZ-19KZ-2 and
BZ-11ST-1, were re-inspected by the NRC and found to have nonconformances
to the design criteria.
This is a Severity Level IV Violation (Supplement II).
g. 10 CFR 50, Appendix B, Criterion V and the Nine Mile Point, Unit-2 FSAR
require that activities affecting quality are conducted in accordance
with documented procedures. Niagara Mohawk Power Corporation procedura
PPNM151 requires that employees report significant deficiencies to the
licensing manager. Further, Stone and Webster Engineering Corporation
~
procedure QS216.2 requires a timely review of significant deficiencies.
Contrary to the above, as of February 10, 1984, NMPC site employees had
not notified the licensing manager of a significant deficiency involving
ITT Grinnell liquid penetrant examinations and SWEC had not conducted a
timely review of a significant deficiency-identified in ITT Grinnell
letter ITT-LTR-4897. Further, no documentation exists to_ verify timely
review- of NMPC QA nonconformance reports as evidenced by NR-349 not
having received a licensing review for reportability until one year and
nine months after issuance.
This is a Severity Level IV Violation (Suppiement II).
Pursuant to the provisions of 10 CFR 2.201, Niagara Mohawk Power Corporation
,uis hereby required to submit to this office within 30 days of the date of the
letter transmitting this Notice, a written statement or explanation in reply,
including for each violation: (1) the corrective steps which have been taken
- 7a~nd the results achieved; (2) the corrective steps which will be taken to ,
lavoid further violations; and (3) the date when full compliance will be
(achieved. Where good cause-is shown, consideration will be given to extending d
~
j cthe response time.
t ,
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.
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.
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.
.-
__ _.. m ma - macequate ca. io. acion control of MT equips.:ent
-
-
84.5 to RCI - welding outside qualified procedure
--
84.6 to.SWEC - Class IE cables pulled into uninspected tray
The CAR's were observed to be issued in accordance with the new QA~ procedures.
Two of the CAR's exercised the new'stop further processing' authority of the QA
organization. The inspector notes a positive improvement in the conduct of NMPC
QA activities as the licensee assumes more control of and responsibility for
construction quality.
8. Construction Deficiency Evaluation
The NRC requires prompt licensee reports of significant construction deficiencies
as contained within 10 CFR 50.55(e). Further interpretive guidance on
construction deficiency reporting is contained within the Inscacticm ad
'
,
Enforcement Manual section. 9900. The inspector reviewed the licensee and
contractor programs to ascertain the implementation of 50.55(e) requirements.
He reviewed the following documents:
NMPC QAP 16.30, " Preparation of Quality Reports on Significant Deficiencies"
--
.
--
NMPC QAP 16.40, " Control and Use of the Nonconfomance Report"
--
Project Procedure PPNM 151, "10 CFR 50.55(e) Significant Deficiencies -
NMPC Evaluation and Reporting"
--
- SWEC
Under 10QA 16.2,
CFR " Notify)ing Clients of Potentially Reportable Deficiencies
50.55(e
Within the licensee's programs the inspector observed that Nonconformance Reports
(NR's) define deficiencies identified by NMPC QA. Presently, the Quality
Assurance procedures require no on-site review to detemine whether an NR is
reportable as a Construction Deficiency Report (CDR), NMPC licensing is respon-
'~
sible for reviewing those NR's to determine reportability. To detemine effective-
ness of the program, the inspector randomly selected several NR's as no ud below
to identify the issuance date and when the reportability review was perfomed:
hR# Issued On Licensing Review On
349 5/24/82 Not performed as of 2/9/24
377 1/7/83 Not perfcmed as of 2/9/84
402 9/22/83 10/28/83
403 9/22/83 10/28/83 -
The above review of the NMPC program indicates a substantial lag i "f ncon-
P rC-
ments for timely review of NR's for reportability consideration .
-
, sistent with the intent of 10 CFR 50.55(e) requirements.
As an example of the contractors program, the inspector obtained r/
'"
.
1984 letter (ITT-LTR-4897) from ITT Grinnell QA Director to SWEC. hra rfg .l
a problem with liquid penetrant testing be revie..ed for reportability. ,
-
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we4 and proceeded to issue a subscquenc
letter dated February 7,1984 to SWEC licensing which requested a 50.55(e)
review of the penetrant problem. This is contrary to QA-16.2 which requires
~
:
the review to be conducted in less than 7 days time. The non-timely review
and action to evaluate the item for reportability is indicative of a deficiency '
within the contractor's reportability system. Additionally, a.lthough NMPC
site employees had knowledge of the liquid penetrant deficiencies discussed
above, a call was not made to the NMPC licensing manacer 1c r qfired by
PPNM151 to provide for prcmpt identifcation and evaluatica 0/ the deficiency.
The above examples of failures of NMPC and SWEC to follow procedures to ensure
prompt evaluation and reporting of significant construction deficiencies is
i
a violation of 10 CFR 50, Appendix B, Criterion V. (24-01-05) ;
The inspector acknowledges that in response to the above concerns NMPC issued
a February 15, 1984 letter to employees which emphasizes the responsibility of
making prompt construction deficiency reports. It is further planned to establish
a site safety review committee to review deficiencies for prompt reportt.bility.
9. Diesel Generator Cranes
The inspector reviewed the following information which pertains to the non-
safety cranes located over the emergency diesel generators:
!
!
--
Regulatory Guide 1.29, " Seismic Desiga Classificatica"
'
--
Specification P251H, " Single Girder Cranes"
,
--
SWEC drawing EM-13, " Diesel Generator Building Machine Locations"
The inspector toured the diesel generator building and noted that numerous
4
safety related items are located in close proximity beneath the cranes,
namely, the emergency diesel generators, class IE raceway, ASME piping and
safety related HVAC items. The licensee's engineering department stated
.
that it was planned to park the non-seismic cranes at the north end of their
runways.
Upon review of the location of the cranes relative to the safaty related items.
the inspector is still concerned that seismic failure of the cran.e or crane
rails could have detrimental results on the operability of othar safety relat .*
equipment. Further, the ~ inspector has previously identified ~tuo non-safety -
instal'ations (control room partitions and reactor buildia: cc;?) which when
analyzed were found to have failure modes which could degrade future safe
operation of the plant.
,
This concern is unresolved pending receipt of analysis to demonstrate that
* safe parking location exists for th'e crane,and analysis to shcw that on a
plant wide basis that non-safety related items have been designed in a irc
that their potential seismic failure will not impair the opercbility of
safety related systems. (84-01-07)
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NINE MILE POINT UNIT #2
.
NRC IDENTIFIED ITEM
. .
_
Item #: 1-84
Inspection Period: 84-01
Type: Potential Violation Date: 2/10/84
*
NRC Inspector: R. A. Gramm Contact: J. L. Dillon/T. R. Loomis
. Item Description:
A) failure of Niagara Mohawk to timely identify and report a condition
found during construction to the NRC as a significant deficiency in
accordance with 10 CfR i0.55(c).
The NRC Inspector noted that NM failed to report - a potential
deficiency involving welds accepted by ITT Grinnell QC (on the SVV
System) and that subsequently were determined to have inadequate
surf ace preparations for liquid penetrant examination. In some cases
the welds also had rejectable indications.
B) failure of Niagara Mohawk to assure that deficiencies found in design
and construction are handled properly and reviewed for reportability
under 10CFR 50.55(e) in a timely fashion.
The NRC inspector noted that NM licensing has failed to review a
backlog of NMQA Nonconformance Reports for reportability under 10CFR
50.55(e). The inspector questioned whether in fact, it is a report *
able deficiency in itself that NM has a backlog of Nonconformance
Reports to review for reportability under 10CfR 50.55(e).
Root Cause:
Corrective Action Plan (Including Implementation Schedule): .
Preventive Action Plan (Including Implementation Schedule):
Responsible Party: A. f. Zallnick/NMPC
Response Required by: 2/17/84
Distribution; D. P. Dise W. D. Baker A. H. Rovetti
A. P. Kordalewski A. f. Zallnick M. G. Pace
J. L. Dillon C. D. Terry T. T. Arrington
L. G. Fenton C. H. Millian J. J. Gallagher
C. G. Beckham NRC Resident Inspector # J. D. May-ITT
W. Morrison M. L. Dunlop-RCI
l l M. Brenner-JCI.
(0306E)
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O
POWER CORPOR ATION
,) NIAGARA MOHAWK
'
QUALITY ASSURANCE PROCEDURE NUMBER 16.30
SUPERSEDES
QAP 16.30, Rev. 3, Feb. 1978
TITLE i '
i
I
O- PREPARATION OF QUALITY REPORTS ON SIGilIFICANT DEFICIENCIES
-
QUALITY ASSURANCE PEPARTMENT
CONCURRENCE
]
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~ Supervisor Supervisor Supervisor
Quality Assurance System Quality Control Quality Control Operations
va , e cuaio, assuiance
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1.0 GENERAL &
J This procedure is to be used in reporting trends adverse to quality, break-
* downs in quality programs, other significant deficiencies, and initiation
,
of a recommendation for a stop work action to the Manager of Quality ,
Assurance.
.
C 2.0 SCOPE
This QAP commences with the recognition of a deficiency which, if it were
to remain uncorrected, would have an adverse affect on saf"ty or reliability
or a deficiency which is of sufficient magnitude to require the attention of
the Manager of Quality Assurance. Also included in this QAP is the
initiation of stop work action by the Quality Assurance Department.
3.0 PURPOSE
( The intent of this QAP is to provide a uniform method of reporting
4 significant problems in a timely manner, to the Manager of Quality
Assurance.
4.0 RESPONSIBILITIES
The observing member of the Quality Assurance Department shall be responsible
for the preparation of the Quality Assurance Significant Deficiency Report
(See Attachment 7.0-a). The appropriate Quality Assurance Departmant
supervisor shall review the report and on concurrence shall sign and fort ard
the report to the Manager of Quality Assurance with a copy to the Quality
Assurance file. .__
RECEIVED
l ((). ,
o Qi,'/ Ally ASSUU.NCE o
" I
.
AUG 011930
.
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QAP 16.30 1
'; Rev. 4 l
' '
-
.
June 1980 l
1
)
The Manager of Quality Assurance shall review the report and decide on
O'- a course of action. For nuclear facilities this action may include
reporting the . condition to the Nuclear Regulatory Coninission (flRC) per
the requirements of Regulations 10CFR50.55e, or 10CFR21.
,
.
5.0 PROCEDURE
5.1 Format (Attachment 7.0-a)
The format of the Significant Deficiency Report shall be as follows:
a) File Number: The appropriate first two positions are to be added per
the NMPC Enaineering File Index.
Stop Work Recommended: If the nature of the consequences of the
b)
condition warrants prompt resolution prior to proceeding with the
work; a stop work order shall be recommended.
c) Facility: The name of the facility involved shall be indicated.
If more than one facility is involved then all facilities shall be
indicated. ,
d) Publication Date: This is the date of the publication of the report.
Organization: This shall identify the organization on which the
Q e)
report is based.
f) Address / City: As appropriate
g) Representative: The individual named shall be the contact in the
organization.
h) Subject: This shall identify the report as, to its general content.
i) Description of Condition: An objectiveThis
description of the conditions
description shall include
which prevail shall be stated.
references to applicable sections of 10CFR50, Appendix B, or other
authoritative criteria as applicable. The anticipated effect of the
condition on safety or reliability shall be stated.
j) Reconc.endation: Correctiic action which is apparent shall be stated.
k) Signatures: The originator shall sign and date the report and on
concurrence, the supervisor shall sign and date the report.
1) Disposition: The action taken on the report shall be noted by the
Manager of Quality Assurance.
m) . Mar,ager's Signature: The Manager shall sign and file the completed
report.
[}
Page 2
I
e. - _ _ _ _ _ _ _ _ - - . _ _ _ - _ _ - _ _ _ _ _ _ _
QAP 16;30
Rev. 4'
, . .s ;
.
-
June 1980
5.2 Distribution
O The Manager of Quality Assurance shall receive the original report plus one
copy of all background material. Other copies may be distributed at his
discretion. With regard to nuclear safety related functions, if he concurs
with the significance of the SDF,, he shall transmit a copy to the Manager *
Generation Engineering for evaluation with regard to the requirements of
10CFR50.55e or 10CFR21. Upon completion of the disposition, the appropriate
Quality Assurance Supervisor shall be notified, either by a copy of the
completed report or by written memo.
5.3 Stop Work Initiation {
'
For quality related problems involving nuclear station design, construction or
operation, there may be a need for the Quality Assurance Department to initiate
a stop work action. In addition to its other functions, the.Significant ,
< Deficiency Report form is to be utilized to document the request by a member
of the Quality Assurance Department, to the Manager of Quality Assurance, to
initiate the stop work action.
For an operating nuclear station, the Manager of Quality Assurance has the
authority to initiate a stop work order through the General Superintendent of
Nuclear Generation for any portion of the nuclear station operations which
appears to be seriously jeopardizing quality. During the design and construction
of a new nuclear station or for a modification / addition to an existing n'iclear
station, the Manager of Quality Assurance has the authority to initiate a
stop work crder through the appropriate project management office for any
portion of the project which appears to be seriously jeopardizing quality.
Stop work orders will usually be orally initiated. After any oral initiation,
as quickly as possible, confirmation by written memorandum shall be supplied
to that person authorized to issue the stop work order. Full documentation
l of all circumstances surrounding any decision to initiate stop work action shall
be retained in the Quality Assurance Department files.
Upon satisfactory resolution of the problem which resulted in the stop work
,
action, work may be restarted. Once again, this start work order may be
orally initiated and must be confirmed by written memorandum. In addition,
there must be adequate information in the Quality Assurance files to
fully explain the final disposition of the problem which led to the stop
work action.
6.0 REFERENCES
a) Federal Regulations 10CFRSO.55e
,
b) Federal Regulation 10CFR21
7.0 ATTACHMENTS
, a) Quality Assurance Significant Deficiency Report form
Page 3
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Attach: 7
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.* lt QAP 16.30
Rev. 4
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June 1980
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STOP WORK ORDER RICOP.".!NOLD 0 YEs O NO
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FAcittit:
QUALITY ASSUR ANCE DEPARTMENT
ly
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1 J - J .. Jl l . PUEL]CATICN CATE:
OR GN!ZAllCN:
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ADDRESS: 7;p *.
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PEFRESENTATIVE:
SL3 JECT:
CE5CRIPT10N cr CONDITION:
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7
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'IN OFFICE MEMORANDUM yoggg, / *
'
SUBJECT POIHirIE 10CFR50.55(e) DATE February 7, 1984
FROM LEPace
#
TO Raysibp Cc m!aki
190 File 8.1.9
esta22
Attached is the Report of a Problon reganiing the ITT Grinnell Liquid
Penetrant Dcunination concern to be evaluated under 10CFR50.55(e).
D G -
M. G. Pace
Pmject Quality Assurance Manager
Attachment -
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C. Zappile cc: R. H. Pinney **55__1 or 1,._
o.osie if ee: ster are:szins nesettu "'
SWFr' OA 12177.50 ,.
5"'"
C' 4
Niarara s hawk Nine Mile Point '"d
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.
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CEsCairfivt TITLE fos Pm08Liu
Liquid Penetrant Dcamination perfonned by ITT Grinnell
strtef*CES: Ca Cat
sisttu SW o a.i s/s,ec. P301C
coui t r orne, N/A'
. _ .
=; * PeC9L tw eas Dis:Ovtaf C 1'*0 Cat t *:E mist e(0, Pn08LE W suwwamT. ACTsom Ta a(N TQ Qaf t
This Report is subnitted to initiate a review under 10CFR50.55(e).
During the CAT Audit, it was revealed that five (5) SVV welds had inadequate
surface preparation which would preclude the acceptable perfonnance of the
required Liquid Penetrant Dcamination.
,
ITT Grinnell is perfonning an evaluation on all welds in the SW Syston,
,,
, and to date, has detennined ntmerous other welds witt inadequate surface
*
preparation. 'Iherefore, the previous liquid penetrant results are question-
k able. Additionally, the re-examination of seven (7) welds has revealed
rejectable linear indications ranging fmn 1/16" to 3/16" in length. 'Ihese
welds had previously been inspected and accepted using the liquid penetrant
technique.
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-[ ][ ] IndustrialPiping,
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P. O. Box 38 5
LYCONG, NEW YORK 13093
>
f.2. #
(315) 349-7528/7529
E
ITT-LTR-4897 %
es
January 25, 1984 e
n
z
to
Stone & Webster Engineering Corporation O'
P.O. Box 63 G5
Lycoming, NY 13093 $
,
ATTN: M.G. Pace
Project Quality Assurance Manager %
Subject: Potential 10CFR50.55(e) Reportable Finding "'
Contract No. NMP2-PC-P301C
Nine Mile Point Nuclear Unit 2
Niagara Mohawk Power Corporation ,
Dear Mr. Pace: r-
L-;
Please be advised that during the re-inspection program fer the CAT
item 23-83, seven welds have been identified by IIT Grinnell as having i
'
Code rejectable linear indication, ranging from 1/16" to 3/16" in length.
,
We feel this warrants your review with respect to 10CFR 50.55(e) reporting. m
!
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Certification for the LP examiners involved have been revoked and these G
welds are being documented on ITT Grinnell Deviation Reports. co
ITTGrinnellwillprovideyouwithalistoftheseweldsas.wellas( [
any other information you may require for your review. We are continuing s g
A
our re-inspection of SVV system welds for the CAT item 23-83 concerns and
will update you on additional rejections. 7
l E i
Very Truly Yours,
'r
3_E
_
-
F. ' . .nkevich
Qu ity Assurance Director
FNZ:pp
cc: R.E. Miller
R.B. Berlien
J. Stevens
J. %%ite
D. Giguere
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J. Pay
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IN'pl COR'RESPONDENCE A[l Ll MOHAWK
.
c- e u :
1 orsInici Syracuse
r n o r.- A. F. Zallnick, Jr.
Iebruary 14, 1984 rlLE CODE
To L' . Morrison " ^ ] { j g r ,- '; D AT E
AlLE P0lfC suaaEc7 f!ine Mile Point Unit 2
NRC Reportability Procedures
,r EB 15 6,. .
l l '
L. . :lD i'.C" *Nll rr" D 2'-
.
On Triday, February 10, I attended a meeting with the NRC Resident inspector,
Mr. Gramm wished
.. '
R. Gramm, and several other Niagara Mohawk representatives.
to discuss some problems he saw with the control and evaluation of potential
pr oblems f or reportability to the NRC. He particularly indicated thatThe we
needed to iraprove our control over the tiraeliness of reportability.
specific example was the problem with the dye-penetrant testing of welds by
Grinnell. This problem was identified atthey the CAT audit in December, and on
felt this was potentially
I January 25, Grinnell informed SWEC thatAs of February 10, this had still not been
reportable under 10CFR50.55(e).
l
reported to the NRC. I
'
After the meeting with Gramm, I discussed this problem with Messrs. Dillon,
Millian, B. Morrison and Beckham.
As a result of these discussions and ,
! i
consicering the problem itself , I recommend that we est e.blish a safety review
cca.cnittee at ine construction siteI to reviewthis
suggest construction
committeedeficiencies
be chaired by and a
.
evaluate them f or reportability.
representative f rom Engineering and contain representatives f rom Quality -
Assurance, Construction and Compliance & Verification. This 9roup would
cvaluate those situations of which Niagara Mohawk is aware, where there is a
_._
< potential reportability under 10:fR50.55(e). Potential reports identified by
this comm,ittee would be directed to Licensing for subsequent coanunication ..
, I with the ( Q . -
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1 believe this approach will resolve Mr. Gramm's major conce n which is to
l
!j
- -- ensure that we have a mechanisrr to provide for timeliness of evaluation and to
( l
' ensure reporting of significant events to the W. --lhis approach would allow
'
evaluations and dec-isions tu be made at the point where the information~if
-
available and the qualifications-fo7sraking the evaluaticr. are also present.
,,-
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C. Beckhain k7 { (< y,b
J. Thomas
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INTERfdAL CORR SPONDENCE
' * "'? "' " M Y NIAGARA
HuMOHAWK
.
, FROM A. F. Zallnick, Jr. ossintCT Syracuse
To All Project Personnel DATE, February 15, 1984 ~
FILE COoE _
SUBJECT Nine Mile Point Unit 2 ,
,
Reporting of Significant Deficiencies
I
, , .
The NRC has recently called to our attention the responsibility of the utility
to report to the NRC significant design, construction or quality assurance
deficiencies that would eventually affect the safe operation of the Nine Mile
Point Unit 2 Nuclear Station. The reporting of significant deficiencies to
the NRC is a requirement of the utility as stated in Title 10 of the Code of
Federal Regulations, Part 50.55(e) and is controlled by Niagara Mohawk via
PPNM 151.
NMPC considers this to be an extremely important responsibility. Failure to
report significant deficiencies may result in enforcement action by the NRC.
This memo is to remind you (no matter what your responsibilities may be) that
if you are aware of a possible significant deficiency in the design,
construction, or quality assurar.ce of the Nine Mile Point Unit 2 Nuclear ,
Station it is your responsibility to alert your supervisor or directly contact
the Nine Mile Point Unit 2 Eclear Licensing Manager (A. F. Zallnick, Jr.,
Ext. 6457).
If you are unsure or unaware of the procedure for evaluation and reporting of
significant deficiencies, please review PPNM 151 in Volume 5 of the Project
Manual. If you have any questions concerning the NRC regulation, the NMPC
procedure, or any situation of which you are aware, you should contact the
Unit 2 Licensing Department.
i
'
l
A. Zallnick, Jr.
AFZ/TL:ja /
xc: All Nuclear Q.A. Personnel
.
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