ML20198D220
| ML20198D220 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 05/13/1986 |
| From: | Bennett W, Jaudon J, Mcneill W, Skow M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20198D195 | List: |
| References | |
| 50-267-86-08, 50-267-86-8, NUDOCS 8605230190 | |
| Download: ML20198D220 (6) | |
See also: IR 05000267/1986008
Text
.
.
APPENDIX C
U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report:
50-267/86-08
License:
Docket:
50-267
Licensee:
Public Service Company of Colorado (PSC)
P. 0. Box 840
Denver, Colorado 80201-0804
Facility Name:
Fort St. Vrain Nuclear Generating Station
Inspection At:
Fort St. Vrain Nuclear Generating Station, Platteville,
Inspection Conducted:
March 3-7, 1986
/
$!/3 8
Inspector:k M[ E.(Skpw, Project Engineer, ProjectDate
Sectis A, Reactor Projects Branch
(paragraphs 1, 2, 3, 4, 6, and 7)
Inspector:
MA/ M
[
8d
R.( Bfnnett, Project Engineer, Project
Date
'
Sectibn A, Reactor Projects Branch
(paragraphs 1, 2, 4, 5, 6, and 7)
! ,
Inspector:
_
, adj
(/Y)
3$
y. p.
cNeill, Project Engineer, Project
Date
L
L Sec ion A, Reactor Projects Branch
(p ragraphs 1, 2, 4, 5, 6, and 7)
ms
-A
4~ 3 8
Approved:
_
udon, Chief, Project Section A,
Dat6
/). f.
L Rea or Projects Branch
%[ $N
O
. - _ _
- - - -
- _ _ -
_ , -
-
_
_ _ _ _
_ _ _ _.__.___ __ _ __
.
..
-2-
Inspection Summary
Inspection Conducted March 3-7, 1986 (Report 50-267/86-08)
Areas Inspected:
Routine, unannounced inspection of the Quality Assurance
Program, Onsite Review Committee, Offsite Review Committee, Offsite Support
Staff, and Tests and Experiments Program.
Results: Within the areas inspected, four violations and one deviation were
identified (paragraphs 3 and 5).
.
r
.
.
-3-
DETAILS
1.
' Persons Contacted
- C
H. Fuller, Station Manager
- L. W. Singleton, Manager, Quality Assurance
- M. J. Ferris, QA Operations Manager
- R. L. Craun, Nuclear Site Engineering Manager
- J. M. Gramling, Supervisor, Nuclear Licensing Operations
.D. Warembourg, Manager, Nuclear Engineering
J. W. Gahm, Manager, Nuclear Production
T. C. Prenger, QA Services Manager
M. Lehr, QA Engineering Supervisor
P. F. Moore, QA Technical Support Supervisor
D. Frye, Nuclear Licensing Specialist
J. Stufflebeam, Executive Secretary /NFSC Clerk
M. Holmes, Nuclear Licensing Manager
J. Johns, Supervisor, Nuclear Licensing Engineering
0. Clayton, Technical Services Engineer
J. Eggebroten, Superintendent, Technical Services Engineering
D.-Webber, Staff Assistant to Station Manager
W. Crain, Superintendent of Maintenance
T. Borst, Support Services Manager / Radiation Protection Manager
P. Collins, PORC Clerk
The NRC inspectors also contacted other licensee personnel including
administrative, clerical, and operations personnel.
- Denotes those attending the exit interview.
2.
Quality Assurance Annual Review
The purpose of this inspection was to ascertain whether the licensee is
implementing a Quality Assurance (QA) program that is in conformance with
regulatory requirements, commitments, and industry guides and standards.
This inspection objective was accomplished by inspection in the following
areas:
Tests and Experiments Program, Onsite Review Committee, Offsite
Review Committee, and Offsite Support Staff.
These areas are addressed in
this report in paragraphs 3 through 6.
The QA program was found to not
have changed significantly since the last inspection of this area in
regard to its organization, personnel and staffing.
A number of QA
program procedures have been revised and reformatted to improve QA
effectiveness. Within this area, no violations, deviations, or unresolved
items were identified.
,
.
.
.
-4-
3.
Onsite Review Committee
The purpose of this inspection was to provide a functional review of the
Onsite Review Committee to determine that the safety-related
responsibilities of the committee are being adequately performed.
The
Onsite Review Committee for Ft. St. Vrain is the Plant Operations Review
Committee (PORC).
The NRC inspector reviewed Technical Specification
Section Number AC 7.1.2; the PORC Charter, Issue 1, dated November 23,
1983; and the minutes for several PORC meetings.
In addition, the NRC
inspector interviewed some PORC members, the PORC clerk and a staff
assistant concerning PORC.
The NRC inspector found that the PORC Charter appears to meet the
requirements of the Technical Specifications.
Those documents that
required a PORC review were sent to PORC for review.
It was noted that
the minutes of the PORC meeting were prepared prior to the meeting by the
PORC clerk; the minutes included a brief description of each item to be
reviewed by PORC.
The documents to be reviewed and copies of the draft
minutes were provided at the PORC meeting.
During discussions with PORC
members, the NRC inspector found that documents requiring review by PORC
were not provided to members prior to the PORC meeting.
At the meeting
attended by the NRC inspector, the PORC Chairman read the description of
each item from the draft minutes to the PORC committee.
If there were
questions from the committee, the document undergoing review was read by
the Chairman and/or one or more of the other members or alternates of the
PORC.
The NRC inspector observed that none of the documents were
individually examined by all of the personnel in attendance.
Also, he
observed that several documents were not examined by any members of the
committee during the meeting.
If PORC took any actions, reached any
conclusions, or made any other changes to the draft minutes, the PORC
clerk retyped the minutes as changed.
The PORC Charter defines review as a " deliberate, critical
examination . . . ." The NRC inspector determined the those documents
identified did not receive a deliberate, critical examination.
This is an
apparent violation (50-267/8608-01).
The number of PORC meeting attendees was found to meet the minimum quorum
required by the Technical Specifications.
By memo dated October 18, 1985,
the PORC Chairman designated four alternate chairmen.
The memo also
identified which members and designated alternate members would attend
each daily PORC meeting.
Each day of the week had a different chairman
and four attendees.
Only two members were scheduled to attend more than
one meeting each week, and that was for only two meetings.
Technical
Specification AC 7.1.2, Section 2, discusses PORC alternates.
It states,
in part, "An alternate chairman . . ,, if required, shall be appointed in
writing by the PORC Chairman to serve in the absence of a chairman . . .
." The NRC inspector concluded that the designation of four alternate
chairmen, each preassigned to a specific day of the week, is an apparent
violation of the Technical Specification (50-267/8608-02).
Additionally, the licensee is committed in the Updated FSAR, Revision 3,
to the provisions of ANSI N18.7-1972, Administrative Controls for Nuclear
. .
,
-5-
Power Plants.
Section 4.5 of ANSI N18.7-1972 states that PORC ". . .
should provide . . . continuing review of the plant operation .
"
...
The NRC inspector concluded that a committee whose personnel substantially
change on a daily basis does not provide for a continuing review of plant
operations.
This is an apparent deviation from the above commitment
(50-267/8608-03).
4.
Offsite Support Staff
The purpose of this inspection was to ascertain whether the offsite
support staff functions are performed by qualified personnel in accordance
with licensee approved administrative controls.
The NRC inspectors
reviewed the Nuclear Guidelines and Policies Manual, organization charts,
and interviewed selected personnel.
In regard to offsite support staff,
there appeared to be a sufficient staff of qualifled personnel to perform
their assigned functions.
Personnel appeared to be aware of their
functions and responsibilities.
Administrative controls were found in
place which describe the responsibilities, authorities, and lines of
communication for the offsite support staff.
Those controls or procedures
addressed design, quality assurance, procurement and interfaces between
onsite and offsite staffs.
No violations or deviations were noted.
5.
Tests and Experiments Program
The purpose of this inspection was to ascertain whether the licensee is
implementing a QA program relating to the control of test and experiments
that is in conformance with regulatory requirements.
In this regard, the
NRC inspectors reviewed Licensee Procedures Q-3, Q-11, TSP-21, and four of
the most recent changes to Technical Specifications.
The NRC inspectors
reviewed the licensee's 10 CFR 50.59 Report Submittal, dated July 22,
1985.
A sample of four Change Notices (CNs) and five tests were selected
from that submittal for further review.
The NRC inspectors review of
those tests and CNs determined that adequate controls were in effect,
safety evaluations were made, and that PORC and Nuclear Facilities Safety
Committee (NFSC) reviews were performed.
However, one problem was found that related to Change Notices.
Deviation
Request DR-85-35-1-H was written against CN 1902 on March 25, 1985.
It
discussed a conflict in cable termination instructions with conditions
found in the field.
The disposition provided for making the changes
required in the field and stated, ". . . a document update will be
incorporated in CN-1798A." A review by the NRC inspectors and the
licensee of CN-1798A did not indicate that the document update had been
accomplished.
This is an apparent violation of 10 CFR 50, Appendix B,
Criterion III (50-267/8608-04).
During review of the latest five 10 CFR 50.59 annual submittals, the NRC
inspectors noted a variation of submittal dates.
Procedure TSP-21,
Issue 2, dated April 21, 1982, required that reports be submitted prior to
March 1 of each year.
The 1983 report was submitted on March 23, 1984,
and the 1984 report was submitted on July 22, 1985.
The 1985 report had
,
., .
-6-
not been submitted as of this inspection.
The licensee stated that the
responsibility for preparing the report was shifted from Technical
Services to Licensing for the 1984 report and that the decision was made
to submit the report at the same time as the FSAR update in July.
A
change or deviation to TSP-21 was not made to support that decision.
Additionally, the licensee stated that TSP-21 was deleted on March 30,
1985, and that a licensing procedure pertaining to the 10 CFR 50.59 report
had not been issued as of this inspection.
The failure to submit reports
at the times required by the procedure is an apparent violation
(50-267/8608-05).
6.
Offsite Review Committee
The purpose of this inspection was to determine if the functions of the
offsite review are being performed in accordance with regulatory
requirements.
The licensee refers to the offsite review committee as the
Nuclear Facilities Safety Committee (NFSC).
In this regard, Technical
Specification AC 7.1.3 and the NFSC Charter, Issue 4, dated January 2,
1984, were reviewed.
The NRC inspectors reviewed the minutes of NFSC
meetings numbered 94, 96, and 99 through 103, reviewed selected portions
of the documents the NFSC reviewed, reviewed NFSC audit reports associated
with meetings 101 and 103, and interviewed selected members of the NFSC
and the NFSC clerk.
In addition, items selected during the PORC and Tests
and Experiments portions of this inspection were followed upon during the
NFSC inspection.
It was verified that NFSC reviewed PORC minutes and
safety evaluations.
The membership of NSFC was verified.
The inspectors
found that the NFSC appeared to function in an effective manner.
For
example, NSFC challenged the PORC evaluation of CN-1876 with regard to an
unreviewed safety question.
Subsequently, the new equipment was placed in
an out-of-service status and an independent review was ordered to resolve
the question.
Documents for review by the committee were distributed to
members with sufficient lead time that questions and comments could be
solicited and returned to the NFSC clerk.
These questions and comments
were then directed to cognizant personnel.
Those personnel in turn
presented a discussion at the NFSC meeting.
The questions and comments
were normally resolved in this manner.
The minutes were not used as an
agenda as with PORC, but were taken at the meetings by the clerk.
While
the minutes of the NFSC meetings appeared to the more complete than the
PORC minutes, the NRC inspectors suggested that the minutes include a
brief explanation of the resolution of the comments and questions.
This
would document the position accepted by the NFSC.
No violations or
deviations were identified in this portion of the inspection.
7.
Exit Interview
An exit interview was held on March 7, 1986, with those personnel denoted
in paragraph 1 of this report.
The NRC senior resident inspector also
attended this meeting.
At the meeting, the scope of the inspection and
findings were summarized.