ML20138G253
| ML20138G253 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 10/10/1996 |
| From: | Cooper R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Danni Smith PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| Shared Package | |
| ML20138G258 | List: |
| References | |
| EA-96-264, EA-96-346, NUDOCS 9610210091 | |
| Download: ML20138G253 (4) | |
See also: IR 05000277/1996006
Text
.- .
.-
- - - - - . _ -. - -
- - . -
. _ - - . -
- . - - . .
. - -
. . . _ -
i
..'
.
'
g
,
%.
.
'
.
October 10, 1996
EA 96-264
EA 96-346
Mr. D. M. Smith,' President
PECO Nuclear
Nuclear Group Headquarters
,
!
Correspondence Control Desk
P. O. Box 195
Wayne, Pennsylvania 19087-0195
!
!
SUBJECT: ROUTINE INTEGRATED INSPECTION 50-277/96-06 AND 50-278/96-06
Dear Mr. Smith:
This report transmits the findings of all the safety inspections conducted by NRC
!
inspectors from July 7,1996, through September 7,1996, at the Peach Bottom Atomic
Power Station, Delta, Pennsylvania. At the conclusion of the inspection, Mr. W. L.
Schmidt discussed the findings with Mr. G. Edwards of your staff. The inspectors based
i
these findings on independent observation of activities, interviews, and document reviews.
'
Your staff continued to operate both units safely and responded well to equipment and
. eather related challenges. Surveillance testing continued to verify system operability and
w
l
l
appropriately identified problems for correction. Of particular note, an auxiliary operator
j
observed and reported that a high pressure coolant injection system steam admission valve
l
did not operate as expected. The operator's attention to detail allowed correction of this
l
valve operation problem. The engineering department continued to support plant
I
operations well. However, we are concerned by your failure to previously identify
l
interactions between the emergency diesel generators during testing and their associated
!
residual heat removal pump tt.at were introduced through plant modifications. Also of
concern is the weak review of technical specification requirements following identification
i
of the interactions. Review of the radiological controls program showed effective
!
implementation of the revised radioactive material shipping regulations and very good
planning and preparation for the Unit 2 outage.
We completed the review of the standby gas treatment single failure issue identified in
inspection Report 95-27 and have issued the enclosed Notice of Violation. The violation
deals with your procedures allowing operation of the system that was unanalyzed in
,
j
accordance with the updated final safety analysis report, in violation of 10 CFR 50.59.
However, because of our review of your staff's completed analysis, no response to the
violation is required. You may, however, respond if you question the facts as outlired in
the Notice of Violation or the enclosed report.
!
Based on the review of the emergency diesel generator and residual heat removal pump
\\
interactions, as discussed above and in the report, one apparent violation was identified
l
!
and is being considered for escalated enforcement action in accordance with the " General
210028
l
9610210091 961010
ADOCK 05000277
G
pop
,
e-.
,--,m
.yy
x
,
. . ,
.
. . , ,
..
1
-
..
Mr. D. M. Smith
2
Statement of Policy and Procedure for NRC Enforcement Action" (Enforcement Policy),
NUREG-1600. Collectively, the inability to meet technical specification surveillance
requirements and the related repetitive modification design and post-modification issues
represent an apparent violation of technical specifications,10 CFR 50.59, and 10 CFR 50
,
Appendix B, Criterion ill - Design Control, and Criterion XVI - Corrective Action.
Accordingly, no Notice of Violation is presently being issued. In addition, please be
advised that the number and characterization of apparent violations as described in the
enclosed inspection report may change as a result of further NRC review.
l
A predecisional enforcement conference to discuss this apparent violation will be
scheduled at a mutually agreeable date. The decision to hold a predecisional enforcement
conference does not mean that the NRC has determined that a violation has occurred or
that enforcement action will be taken. This conference is being held to obtain information,
to enable the NRC to make an enforcement decision, such as a common understanding of
the f acts, root causes, missed opportunities to identify the apparent violation sooner,
l
corrective actions, significance of the issues and the need for lasting and effective
corrective actions. In particular we expect you to address failures of you. programs in the
areas of design control and verification of installed modifications to detect these problems.
In addition, this is an opportunity for you to point out any errors in our inspection report
and for you to provide any information concerning your perspectives on 1) the severity of
the violation, 2) the application of the factor:; that the NRC considers when it determined
the amount of a civil penalty that may be assessed in accordance with section VI.B.2 of
the Enforcement Policy, and 3) any other application of the Enforcement Policy to this
case, including the exercise of discretion in accordance with Section Vil of the policy.
You will be advised by separate correspondence of the results of our deliberations on this
matter. No response regarding this apparent violation is required at this time.
In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice", a copy of this letter
and its enclosure will be places in the NRC Public Document Room.
We appreciate your cooperation.
Sincerely,
ORIGINAL SIGNED BY:
Richard W. Cooper,11, Director
Division of Reactor Projects
Docket / License No. 50-277/DPR-44
50-278/DPR-56
Enclosure:
1. Appandix A, Notice of Violation
2. NRC Rcgion I Combined Inspection Report 50-277/96-06 and 50-278/96-06
cc w/ encl:
. . - . -
_ - - -
.. -
.
-
-
.. ..
,
.
.
..
.
l.
.
f
Mr. D. M. Smith
3
<
cc w/enci
'
'
G. A. Hunger, Jr., Chairman, Nuclear Review Board and Director, Licensing
G. Rainey, Senior Vice President, Nuclear Operations
T. Mitchell, Vice President, Peach Bottom Atomic Power Station
D. B. Fetters, Vice President, Nuclear Station Support
T. Neissen, Director, Nuclear Quality Assurance
.
C. D. Schaeffer, External Operations - Delmarva Power & Light Co.
G. Edwards, Plant Manager, Peach Bottom Atomic Power Station
G. J. Lengyel, Manager, Experience Assessment
J. W. Durham, Sr., Senior Vice President and General Counsel
i
P. MacFarland Goelz, Joint Generation, Atlantic Electric
B. W. Gorman, Manager, External Affairs
R. McLean, Power Plant Siting, Nuclear Evaluations
J. Vannoy, Acting Secretary of Harford County Council
R. Ochs, Maryland Safe Energy Coalition
J. H. Walter, Chief Engineer, Public Service Commission of Maryland
L. Jacobson, Peach Bottom Alliance
'
Commonwealth of Pennsylvania
State of Maryland
'
TMI - Alert (TMIA)
,
i
1
I
4
'
- .
. .
-
,o
.
,
,
,.
.
Mr. D. M. Smith
4
.
Distribution w/ encl:
Region i Drcket Room (with concurrences)
K. Gallagher, DRP
Nuclear Safety Information Center (NSIC)
D. Screnci, PAO
NRC Resident inspector
PUBLIC
Distribution w/ encl: (Via E-Mail)
W. Dean, OEDO
'
J. Lieberman, OE (OEMAIL)
R. Zimmerman, ADPR, NRR
F. Davis, OGC
A. Nicosia, OGC
J. Shea, NRR
j
J. Stolz, PDI-2, NRR
Inspection Program Branch, NRR (IPAS)
R. Correia, NRR
R. Frahm, Jr., NRR
D. Holody, EO, RI
DOCUMENT NAME a:\\9606.PB
To receive a copy of this document, Indicate in the box: "C" = Cpy without attachment / enclosure
"E" = Copy with attachment / enclosure
"N* = No copy
/
f }
,
OFFICE
RI:DRP
RI:DF P
l
p RI:DRP /fpf
ug
,
,
NAME
WSchmidtAf Mr
WPdspjhk\\\\
RCoope//gj'
"
DATE
10/T/96
10/)(f96
10f0/96
OFFICIAL RECORD COPY