ML20237L649
| ML20237L649 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 09/02/1987 |
| From: | Russell W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Mroczka E CONNECTICUT YANKEE ATOMIC POWER CO. |
| Shared Package | |
| ML20237L653 | List: |
| References | |
| NUDOCS 8709090019 | |
| Download: ML20237L649 (4) | |
See also: IR 05000213/1986099
Text
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'02 SEF 1987
Docket No. 50-213
Connecticut Yankee Atomic Power Company
ATTN: Mr. E. J. Mroczka
Senior Vice President - Nuclear
Engineering and Operations Group
P. O. Box 270
Hartford, Connecticut 06141
Gentlemen:
Subject: Systematic Assessment of Licensee Performance (SALP) Report Number
50-213/86-99 and Your Reply Letter Dated July 17, 1987
This letter refers to the March 1,1986 through March 31, 1987 SALP for Haddam
Neck, initially forwarded to you by our June 10, 1987 letter (Enclosure 1).
This SALP was discussed with you and your staff at the Haddam Neck site on
June 18,1987 (see Enclosure 2 for attendees). We have reviewed your
July 17, 1987 written comments (Enclosure 3) and herewith transmit the amended
report (Enclosure 4).
We appreciate your positive overall response to this SALP, Worth particular
note, we feel, are your discussion of operator contributions to trips, main-
tenance performance, containment integrity, licensing priorities / schedules,
site and corporate interaction, and fire protection.
We have considered your disagreement with the Category 2 rating in emergency
preparedness. However, our review affirms that rating and the amended SALP is
the same, in all areas, as the version previously forwarded to you.
We agree with your comment on maintaining an open dialogue on performance trends,
even though it is premature to draw conclusions before performing the next SALP.
My staff is available to periodically discuss apparent trends with you after
the current outage ends. As time permits, I plan to participate in such
discussions.
Thank you for your cooperation.
Sincerely,
Original Signed By
VILLIAM T. RUSSELL
1kdm
rator
8709090019 070902
ADOCK 05000213
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OFFICIAL RECORD COPY DL50-213/86-99-FINAL - 0001.0.0
08/24/87
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Connecticut Yankee Atomic Power Co.
2
'02 SEP 1987
1
1
Enclosures:
1.
NRC Letter, W. T. Russell to E. J. Mroczka, June 10, 198'7
2.
SALP Management Meeting Attendees, June 18, 1987
3.
Connecticut Yankee Atomic Power Company Letter, E. J. Mroczka to
USNRC, July 17, 1987
4.
NRC Region I Amended Systematic Assessment of Licensee Performance (SALP)
Report No. 50-213/86-99
cc w/encls:
D. B. Miller, Station Superintendent
D. O. Nordquist, Manager of Quality Assurance
R. M. Kacich, Manager, Generation Facilities Licensing
W. D. Romberg, Vice President, Nuclear Operations
Gerald Garfield, Esquire
Chairman Zech
Commissioner Roberts
Commissioner Bernthal
Commissioner Carr
d
Commissioner Rogers
Vandana Mathur, McGraw nill Publications (2 copies)
Public Document Room (PDR)
local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
NRC Resident Inspector
State of Connecticut
bcc w/encls:
Region I Docket Room (with concurrences)
Management Assistant, DRMA (w/o encl)
J. Taylor, DED0
W. Russell, RI
J. Allan, RI
D. Holody, RI
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K. Abraham, PA0 (2 copies)
I
W. Johnston, DRS
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T. Martin, DRSS
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Section Chief, DRP
1
J. Shedlosky, SRI, Millstone 1&2
{
T. Rebelowski, SRI, Millstone 3
J. Akstulewicz, LPM, NRR
R. Bores, DRSS
-
Management Meeting Attendees
DRP WISHLIST Coordinators (w/o encis)
1
0FFICIAL RECORD COPY DL50-213/86-99-FINAL - 0002.0.0
08/24/87
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Connecticut Yankee Atomic Power Co.
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02 SEP 1987
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0FFICIAL RECORD COPY DL50-213/86-99-FINAL - 0003.0.0
08/24/87
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Connecticut Yankee Atomic Power Company 2
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Enclosures:
1.
NRC Letter, W. T. Russell to E. J. Mroczka, June 10, 1987
2.
SALP Management Meeting Attendees, June 18, 1!37
3.
Connecticut Yankee Atomic Power Company Letter, E. J. Mroczka to
USNRC, July 17,.1987
4.
NRC Region I Systematic Assessment of Licensee Performance (SALP)
,
Report No. 50-213/86-99
cc w/encis:
D. B. Miller, Station Superintendent
D. O. Nordquist, Manager of Quality Assurance
R. M. Kacich, Manager, Generation Facilities Licensing
W. D. Romberg, Vice President, Nuclear Operations
'
Gerald Garfield, Esquire
Chairman Zech
Commissioner Roberts
Commissioner Bernthal
Commissioner Carr
Commissioner Rogers
Vandana Mathur, McGraw-Hill Publications (2 copies)
Public Document Room (PDR)
Local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
NRC Resident Inspector
State of Connecticut
bec w/encis:
Region I Docket Room (with concurrences)
Management Assistant, DRMA (w/o encl)
'
J. Taylor, DEDD
W. Russell, RI
J. Allan, RI
D. Holody, RI
K. Abraham, PA0 (2 copies)
W. Johnston, DRS
T. Martin, DRSS
Section Chief, DRP
J. Shediosky, SRI, Millstone 1&2
T. Rebelowski, SRI, Millstone 3
J. Akstulewicz, LPM, NRR
R. Bores, DRSS
Management Meeting Attendees
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DRP WISHLIST Coordinators (w/o encis)
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ENCLO50RE 1
tJNITED STATES
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NUCLEAR REGULATORY COMMISSION
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REGION I
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$31 PARE AVENUE
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KING OF PRUS$1A, PENN5YLVANI A 19406
Decket No. 50-213
JUN 101987
Connecticut Yankee Atomic Power Comptny
ATTN: Mr. E. J. Mroczka
Senior Vice President - Nuclear
Engineering and Operations Group
P. D. Box 270
Hartford, Connecticut 06101
.
Gentlemen:
9,
Subject:
Systematic Assessment of Licensee Performance (SALP) Report No.
50-213/86-99
On May 14, 1987, as documented in the enclosed SALP Board Report, the NRC Region
I SALP Board assessed the performance of the Haddam Neck Nuclear Power Station for
the period from March 1, 1986 through March 31, 1987.
The SALP Board found gener-
ally acceptable performance which was directed toward safe operation.
However,
because Plant Operations received a Category 2 rating and Fire Protection was rated
as Category 3, overall facility performance has declined since the last SALP.
A meeting at the Haddam Neck Site has been separately scheduled to discuss both
the Haddam Neck and the Millstone Unit 3 assessments.
(The Millstone Unit 3 SALP
Board report was previously forwarded to you by letter dated May 14,1987.) This
meeting is intended to provide a forum for candid discussions of the performance
evaluation.
At the meeting, you should be prepared to discuss our assessments,
your plans to improve performance, and the status of your corrective action program
for Fire Protection.
Additionally, you may provide written comments within 30 days
after the meeting.
Following our meeting and receipt of your response (s), the SALP reports and your
response (s) will be placed in the NRC Public Document Room.
Thank you for your letter dated March 10, 1987 informing us of the implementation
of corrective actions on the previous Haddam Neck SALP report.
Your cooperation is appreciated.
Sincerely,
i
William T. Russell
Regional Administrator
l
Enclosure:
NRC Region I SALP Report 50-213/86-99
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Connecticut Yankee Atomic Power' Company 7 '
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cc w/ enc 1:
D. B. Miller, Station Superintendent
D. O. Nordquist, Manager of Quality Assurance
R. Kacich, Generation Facilities Licensing
W. D. Romberg, Vice President, Nuclear Operations
Gerald Garfield, Esquire
Public Document Room (PDR)
Local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
NRC Resident Inspector
State of Connecticut
Chairman Zech
Commissioner Roberts
Commissioner Bernthal
Commissioner Asselstine
q
Commissioner Carr
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INP0 (Record Center, INPO)
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ENCLOSURE 2
NRC/ NORTHEAST NUCLEAR ENERGY COMPANY MANAGEMENT MEETING
JUNE 18, 1987
NAME
TITLE
NRC Region I
William F. Kane
Director, Division of Reactor Projects (DRP)
Ebe C. McCabe
Chief, Reactor Projects Section 3B, DRP
J. Thomas Shedlosky
Senior Resident Inspector, Millstone 3
Paul D. Swetland
Senior Resident Inspector, Haddam Neck
Andra A. Asars
Resident Inspector, Haddam Neck
NRC, Nuclear Reactor Regulation (NRR)
Cecil 0. Thomas
Director, Integrated Safety Assessment
Francis M. Akstulewicz
Haddam Neck Project Manager, PDISA
Robert L. Ferguson
Millstone 3 Project Manager, PDI-4
Elizabeth L. Doolittle
Millstone 3 Project Manager, PDI-4
State of Connecticut
Kevin T. McCarthy
Director, Radiation Safety, Department of Environmental
i
Protection
Northeast Nuclear Energy Company - Corporate
William B. Ellis
Chairman and Chief Executive Officer
Bernard M. Fox
President, Northeast Utilities
John F. Opeka
Executive Vice President - Engineering and Operations
Edward J. Mroczka
Senior Vice President - Nuclear Engineer and Operations
Wayne D. Romberg
Vice President - Nuclear Operations
Richard P. Werner
Vice President - Generation Engineering and Construction
C. Frederick Sears
Vice President - Nuclear and Environmental Engineering
0. Peter Terragna
Vice President - Corporate Performance Services and
Organizational Control
E, Randolph Foster
Director, Generation Construction
Donald 0. Nordquist
Director, Quality Services
Grant D. Baston
Director, Nuclear Engineering and Operations
Reginald C. Rodgers
Director, Nuclear Engineering
G. Leonard Johnson
Director, Generation Engineering and Design
J. Malcolm Black
Director, Nuclear Training
Thomas J. Dente
Superintendent, NUSCO Nuclear Operations
Richard M. Kacich
Licensing Manager
Albert J. Hajek
Manager, Corporate Performance Services and Organizational
Control
Generation Facilities Licensing Supervisor
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Enclosure 2
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Northeast Nuclear Energy Company - Corporate (Cont.)
Jack R. Barnett"
Generation Facilities' Licensing
George R. Pitman'
Connecticut Yankee NRB Chairman.
Mario'V. Bonaca
Millstone 3 NRB Chairman
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Robert N. Smart
Millstone 2 NRB Chairman
Stuart A. Thickman:
Supervisor, Nuclear Safety Engineering
James'P. Hoben
Corporate Performance-Services and Organizational Control
Haddam Neck Plant
Donald B. Miller
Station Superintendent
Gary H.- Bouchard>
Unit-Superintendent
Eric A. DeBarba
Station Services Superintendent
Leo J. Nadeau :
Manager, Generation Projects
Walter.L. Varney
Manager, Plant Quality Services
-Roy_E; Brown
~0perations Supervisor
Donald J. Ray. .
Engineering Supervisor
c
William D. Bartron
Maintenance Supervisor
- Bruce R. Danielson
Instrument and Control Supervisor
Harold E.-'Clow
Health Physics Supervisor
. Michael D. Quinni
Chemical Supervisor
Walter.E. Heining-
-Quality Assurance Specialist-
. William F. Nevelos'
Radiation Protection Specialist
Peter A. Marchese
Security Supervisor
~ James H. Asburner-
Supervisor, Generation Construction
Thomas Kazukynas;
Fire Protection Engineer
Anthony E. Nericcio
Public Information Specialist
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Millstone Site
Stephen E. Scace
Station Superintendent
Carl H. Clement
Unit Superintendent
Harry F. Haynes
Station Services Superintendent
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Kenneth L. Burton
Operations Supervisor
James S. Harris
Engineering Supervisor
Ronald W. Rothgeb
Maintenance Supervisor
Ronald Sachatello
Radiation Protection Supervisor
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ENCLOSURE 3
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CONNECTICUT YANKEE ATOMIC POWER COMPANY
B E R L I N.
P o Box 270 * HARTFORD, CONNECTICUT 061414270
h*EPHONE
2034 % 4000
July 17,1987
Docket No.30-213
B12592
Re: SALP
U.S. Nuclear Regulatory Commission
Attn: Document Control Desk
Washington, D.C. 20$55
Gentlemen:
Haddam Neck Plant
Systematic Assessment of Licensee Performance
.
The Staff recently forwarded the SALP Board Report (l) for the 13-month period
ending March 31,1987 for the Heddam Neck Plant. Subsequent to receipt of the
SALP Board Report, a meeting was held on June 18,1987 between members of
the Staff and members of Connecticut Yankee Atomic Power Company
(CYAPCO).
The purpose of this letter is to responc' '.-> and comment on the findings of the
SALP Board with particular emphasis on the Board recommendations for the
individual evaluation categories.
Attachment A to this letter contains the
CYAPCO response to each of the Board's recommendations for the Haddam Neck
Plant.
In reviewing the SALP report, CYAPCO finds it disappointing that the NRC
considers that overall facility performance has declined since the last SALP
evaluation period. We believe that significant initiatives have taken place to
further improve plant performance. CYAPCO finds much in the text of the
report to support this conclusion. However, if CYAPCO is not headed in the
right direction in the judgement of the NRC Staff, this must be identified so that
a mutual understanding and appropriate corrective actions can be taken
promptly,
i
(1)
W. T. Russell letter to E. J. Mroczka, "SALP Report No. 50-213/S6-99,"
dated June 10,1987.
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U.S. Nuclear Regulatory Commission
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July 17,1987
H
Accordingly, CYAPCO wishes to maintain an open dialog with the NRC
concerning its current performance trend.
CYAPCO's goal is to return to
Category 1 performance in all functional areas. CYAPCO believes that this
goal is attainable.
Very truly yours,
CONNECTICUT YANKEE ATOMIC POWER COMPANY
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Seniorflice President
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cc:
W. T. Russell, Region I Administrator
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F. M. Akstulewicz, NRC Project Manager, Haddam Neck Plant
J. T. Shediosky, Senior Resident inspector, Haddam Neck Plant
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Docket No.30-213
B12392
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Attachment A
Connecticut Yankee Atomic Power Company
Haddam Neck Plant
Response to SALP Report
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July,1987
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Functional Area:
PLANT OPERATIONS
Board Recommendatig: Correct the causes of operator contribution to
unnecessary trips.
Response:
Two causes were identified for operator contribution to unnecessary trips. One
was operator error during startup, and the other was inadequate coordination
between the operators and technicians performing the work.
The circumstances surrounding the operator error during startup indicated that
this was an isolated occurrence. A turbine test engineer, concerned over getting
the turbine through its critical speed, rushed the operator during turbine startup.
Steam demand increased too quickly, causing a plant trip.
While the test
engineer's concern over excessive turbine vibration is appropriate, the
overzealous manner in which he expressed this concern was not. The Operations
Supervisor reviewed this event with all Operations Department personnel,
stressing the responsibility of the operators to operate plant equipment properly
regardless of the circumstances.
The two trips that were due to inadequate coordination between the operators
and working technicians indicated that there was a need to formalize the
interface between these groups.
Accordingly, a new station procedure was
developed to provide a formal review of work conducted on the back shif ts. Key
to this review is a checklist which is completed by the technician and the Shif t
Supervisor prior to initiation of work. This checklist is intended to help the Shif t
Supervisor and technician identify potential problems with the pre posed work
before it is actually performed, thus minimizing the chances for a unnecessary
trip.
In order to continue to improve the operator training program, a Licensed
Operator Continuing Training Program Implementing Procedure (TPIP) was
issued in September,1986. This procedure, in concert with the Nuclear Training
Manual, provided detailed programmatic and administrative requirements related
to training content, examinations, removal from shift for unsatisfactory
performance, scheduling, departmental duties, instructors qualifications, training
effectiveness, and records. Copies of this procedure were informally provided to
both the Hoddam Neck Plant Resident inspector and Region 1 PWR-Westinghouse
Lead Operator Licensing Examiner in the October,1986 time [11
rpme. In addition,
the procedure was transmitted to the NRC for formal review.
Additionally, A
NUSCO QA Su-veillance was performed in December,1986 indicating that the
administrative controls were in place at that time. sSuch measures should help to
decrease the number of operator errors that occur.
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E. 3. Mroczka
letter
to
C. I. Grimes,
"R evised Lice. 2d Operator
Requalification Training Program Procedures and Program Descriptions,"
dated December 8,1986.
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Functional Area:
RADIOLOGICAL CONTROLS
Board Recommendation: Assure effective site and corporate coordination and
pre-planning of radiological controls activities.
Response:
Northeast Utilities, as has been previously stated, is actively pursuing
improvement of the corporate / site interface.
This effort includes the
Radiological Controls Area, and has already resulted in a joint committee being
formed to review and upgrade the station Health Physics procedures,
improved cooperation has also been evident in the ALARA planning for the 1987
Refueling Outage. A joint NUSCO/CYAPCO committee has reviewed virtually
all of the schec'uled major construction projects for ways to reduce radiation
exposure.
This planning has yielded significant reductions in the exposure
estimates and hence lowered the radiation exposure goal for the outage.
Initiatives to improve the site / corporate interface will continue, including an
increase in the effectiveness of the corporate audit / appraisal process.
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Functional Area:
MAINTENANCE AND MODIFICATIONS
Board Recommendation: Consider
measures
to
improve
equipment
and
maintenance personnel performance in order to prevent
unnecessary trips.
Response .
A new station procedure to improve coordination for work on back shif ts that
could result in a plant trip has previously been described in the response under
Plant Operations. In addition to this, any new measures that can reduce plant
trips will be given priority consideration. The obvious benefits of reducing the
number of unnecessary trips makes this policy a prudent one.
The final paragraph of this Functional Area cited personnel errors, instances of
ineffective maintenance, procedural and documentation inadequacies, and the
maintenance backlog as factors which prevented the attainment of overall
maintenance excellence. With the exception of the backlog, CYAPCO feels that
these problems are all related to deficiencies in procedural quality and
adherence. This has been a common theme of recent plant evaluations both
internal and external. CYAPCO is addressing this problem on several fronts,
including procedure upgrades,
improved training, increased supervisory
involvement, and increased station management emphasis on procedural
compliance. Efforts are currently underway in each of these areas. In addition,
- CYAPCO has become involved in human performance evaluation systems and
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root cause analysis techniques to better evaluate plant occurrences. CYAPCO
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expects these efforts to yield tangible results during the present SALP period.
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With regard to the maintenance backlog, it is CYAPCO's policy to diligently
pursue reduction of the backlog on an ongoing basis. As stated in the SALP
Report, the backlog has been reduced 17% during the recently completed SALP
evaluation period. This is an indication that the policy is effective.
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Functional Area:
SURVEILLANCE
Board Recommendation: Assure
that
acceptable
containment
leakage
is
maintained throughout operating cycles.
Response:
As noteri in the SALP text, containment leakage in excess of allowables is
currently being addressed. Additional containment isolation valves are being
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added to those penetrations which historically have experienced excessive
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leakage. New hardware which will allow the use of improved test methods is
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also being installed on some penetrations. In addition, new isolation valves are
being installed in the service water system which will prevent river water
contamination of the component cooling water system during survell!ance
testing.
Contamination of the component cooling water system has been
identified as a cause of many leaky isolation valves. Finally, a full pressure
Integrated Leak Rate Test will be performed at 40 psig during the 1987 refueling
outage. CYAPCO is committed to assuring containment integrity, and believes
that its actions demonstrate this commitment.
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Functional Area:
Board Recommendation: None.
Response:
CYAPCO does not agree with the SALP evaluation in this functional area. While
the details given in the text are accurate, we conclude that they do not support
the Category 2 rating.
The exercise deficiencies noted, while accurate, are in our estimation of very
low significance. They are the types of human errors that one would expect
from individuals involved in a task which they perform infrequently. As noted in
the SALP report, there were several strengths exhibited by these same
individuals.
The NRC concern over a lac' of procedural definition of the DSEO/NRC DSO
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interface is being addressed as noted in the SALP report.
This concern is,
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however, an artificiality in our opinion since the DSEO and NRC DSO would be
Ic,cated in very close physical proximity during an actual event (in adjacent
rooms in the EOF). Certainly, the NRC DSO would be kept abreast of the
situation along with the rest of the Emergency Operation Center staff.
The NRC concern over augmentation was shared by current plant management;
hence the unannounced drill on March 24, 1987. The unaccept<ble results of this
licensee initiated test were, as noted in the text, dealt with immediately and
decisively by plant management.
Given the significant, licensee initiated improvements in the Emergency
Preparedness area, coupled with two well executed exercises in 1986 and 1987,
C YAPCO's reaction to the present evaluation is one of disappointment.
CYAPCO will continue to investigate future improvements to further upgrade
the program.
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Functional Area:
SECURITY. AND SAFEGUARDS .
Board Recommendation: None.
Response:
None.
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Functional Area:
REFUELING AND OUTAGE MANAGEMENT
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Board Recommendation: None.
Response:
CYAPCO agrees that the initiatives taken to date, while significant, must be
proven through use during the 1987 Refueling Outage. Performance during this
outage will demonstrate that the changes have been effective.
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Functional Area:
ASSURANCE OF QUALITY
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Board Recommendation: None.
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Response:
CYAPCO management intends to continue and expand the positive initiatives
cited in the SALP text. Procedures and personnel adherence to these procedures
are being closely scrutinized.
CYAPCO believes
that its overall trend is
positive and plans to build on this foundation.
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Functional Area:
TRAINING AND QUALIFICATION EFFECTIVENESS
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Board Recommendation: Nme.
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Response:
Our response concerning the Plant Operations functional area addresses the
implementation of operator requalification program administrative controls.
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Functional Area:
LICENSING ACTIVITIES
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' Board Recommendation: Develop overall approach for planning submittals to
assure they are fully supported and submitted in a
timely fashion.
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Response:
'
We believe that communications are being improved between the NRC and
CYAPCO on outstanding information requests and other licensing actions,
thereby allowing timely decisions to be made to resolve outstanding issues. One
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recent example of this effort is the establishment of periodic meetings with the
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. NRC Project Manager to prioritize and schedule current licensing issues in a
sanner that is supportive of both the NRC Staff's schedule and our available
This overall approach for planning submittals on current licensing
resources.
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issues provides greater assurance that information requests are fully supportive
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and submitted in a timely fashion. Long-standing NRC concerns with respect to
Technical Specification upgrades for NUREG-0737 issues and degraded grid
voltage have recently been placed in the high-priority category.
We have continuallydtrived to provide comprehensive, thorough, and technically
sound submittals.
In cases where the NRC Staff has required additional
information, we have been quick to respond to the request with follow-up
conference calls, meetings, or additional written submittals.
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As discussed briefly during the June 18, 1987, SALP meeting, we note that
voluntsry initiatives such as the Probabilistic Safety Study and ISAP analyses
may',dentify weas of plant vulnerability which were not previously analyzed.
Therefore, this may result in the need for prompt expenditures of both CYAPCO
and NRC, resources, including a temporary waiver or an emergency license
amendment. While we certainly wish to keep such evolutions to a minimum,
safety considerations occasionally dictate otherwise. We request the NRC to
take this into account in evaluating our performance in this functional area,
in summary, we bellese that the licensing activities associated with the Haddam
Neck Plant derrionstrate that an overall approach for planning submittals is in
place.
CYAPCO management is firmly committed to providing the proper
resources and direction necessary to provide assurance that all licensing issues
are fully supported and submitted in a timely fashion, and the resultant
commitments are fully implemented.
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Functional Area:
ENGINEERING SUPPORT
Board Recommendation: Improve communication and coordination between the
site and corporate staffs.
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Response:
During the SALP period, major improvements in communication and coordination
between the site and corporate staff have occurred in the area of outage
modifications. The ties that have been established during this effort are being
extended to other areas, most notably Fire Protection. This evolutionary process
is highly endorsed by management and will continue.
The text of the SALP also stated that training for site engineering personnel is
deficient but that a training program was under development. This program is
now developed and is awaiting INPO accreditation. In the interim, the training is
being administered using the newly developed program.
Pre-operational testing has been an area of concern for some time at the
Haddam Neck Piant. In response to this, a new procedure is being finalized that
will provide specific, detailed guidance in this important area.
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Functional Area:
FIRE PROTECTION
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Board Recommendation: Take appropriate ' action
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Improve management
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involvement in the fire r '.ection area and enhance the
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interface between the site and corporate staffs.
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Response:
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CYAPCO iv Sommitted to improving the Fire Protectics Program.
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\\cosmitment ss evidenced by such significant items as:
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Construction), of a. new switchgear room as part of the Appendtx R
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Contracting a consulting firm to perform d licensing commitment review;
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Conducting ongoing fire protection system code compliance reviews;
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Perhaps most significant for' the long term improvement in the fire protection
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area is the addifica of .a; full time fire protection engineer to the plant
engineering staff. This :aG:vidual was previously loc >ted in the corporate' Fire'
Protection Gro.sp, and has already itnproved markedly the site / corporate
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interface in fire prov;ction. Most importantly, this individual will provide the
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continuity that was laching in the previous approach to this issle! CYAPCO
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believes that the actioris it is taking will result ultimately in 'a strong firs
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protection program.
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