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{{Adams | |||
| number = ML20138H772 | |||
| issue date = 12/27/1996 | |||
| title = Forwards Insp Rept 50-277/96-06 & 50-278/96-06 on 960707-0907 & Forwards Notice of Violation | |||
| author name = Cooper R | |||
| author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) | |||
| addressee name = Smith D | |||
| addressee affiliation = PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC | |||
| docket = 05000277, 05000278 | |||
| license number = | |||
| contact person = | |||
| document report number = EA-96-264, EA-96-346, NUDOCS 9701060228 | |||
| package number = ML20138H777 | |||
| document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE | |||
| page count = 3 | |||
}} | |||
See also: [[see also::IR 05000277/1996006]] | |||
=Text= | |||
{{#Wiki_filter:, | |||
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December 27,1996 | |||
EA 96-264 | |||
EA 96-346 I | |||
i | |||
Mr. D. M. Smith, President l | |||
PECO Nuclear ! | |||
Nuclear Group Headquarters | |||
Correspondence Control Desk | |||
P. O. Box 195 | |||
Wayne, Pennsylvania 19087-0195 | |||
l | |||
SUBJECT: NOTICE OF VIOLATION | |||
(NRC INSPECTION REPORT NO. 50-277/96-06 AND 50-278/96-06) , | |||
1 | |||
! | |||
Dear Mr. Smith: j | |||
i | |||
This letter refers to the NRC inspection conducted from July 7,1996 to September 7,1996, l | |||
' | |||
at the Peach Bottom Atomic Power Station facility and to the apparent violation described in | |||
the report associated with the emergency diesel generator and residual heat removal pump | |||
interactions. The findings of the inspection were discussed with members of your staff during | |||
an exit meeting on September 19,1996. In addition, the NRC inspection report was sent to , | |||
you with our letter, dated October 10,1996. On December 6,1996, a Predecisional ! | |||
Enforcement Conference was conducted with you and members of your staff to discuss the ; | |||
related violation, its causes, and your corrective actions. | |||
2 | |||
Based on the informe' an developed during the inspection, and the information provided during 4 | |||
the conference, or Violation of NRC requirements was identified. The violation is set forth ! | |||
in the enclosed f.otice of Violation. It involves the failure to verify the adequacy of the | |||
modification der gn of Modification P-0231 prior to implementation as required by 10 CFR 50, | |||
Appendix B, Criterion Ill, Design Control. Modification P-0231 provided for automatic | |||
emergency diesel transfer from the droop to the isochronous mode of operation. | |||
Modificatir,n P-0231 was first installed for two diesel generators in June 1995, but a full | |||
understareding of its effects on other systems was not realized until June 1996, when | |||
simulator runs were made. In cases where the plant response changes, the adequacy of the | |||
new design must be verified, as required by 10 CFR Part 50, Appendix B, Criterion lil, and as | |||
specified in ANSI N45.2.11-1974, to which you are committed. We are particularly concerned | |||
that your staff did not understand all of the effects of the modification on the facility prior to | |||
implementation of the modification. In your response to this letter, please pay particular | |||
attention to what corrective actions you will put in place to ensure that the effects of future | |||
modifications are understood prior to implementing them. { | |||
} | |||
During the predecisional enforcement conference we discussed at length the scenario that | |||
involved an emergency diesel generator operating in the test mode and the effect of a | |||
subsequent loss of coolant accident signal on the operability of the associated offsite power | |||
source. It is our understanding that, until June 1996, your staff assumed that the emergency | |||
N On O | |||
9701060228 961227 | |||
PDR ADOCK 05000277 g*M | |||
G PDR | |||
f | |||
s . | |||
. | |||
. | |||
Mr. D. M. Smith 2 | |||
pumps would load onto the bus consistent with their assigned time delay sequences. During | |||
the predecisional enforcement conference, your staff gave the position that,in consideration | |||
of the actual starting sequence of the pumps, no specific evaluation would have been | |||
necessary for this scenario because no credit was taken in the licensing basis for the diesel | |||
generator bein0 on the bus. The point does not apply since you are required to understand | |||
the effects of design changes on the overall facility design prior to implementation of the | |||
modification. | |||
it is also important to note that we recognize that your staff self-identified this issue during | |||
simulator runs in June 1996, and subsequently, in your "PBAPS EDG Licensing Basis," dated | |||
July 16,1996, your staff completed verification of the design of the modification. We will | |||
review this document during a future inspection of your licensed activities. | |||
You are required to respond to this letter and should follow the instructions specified in the | |||
enclosed Notice when preparing your response. The NRC will use your response, in part to | |||
determine whether further enforcement action is necessary to ensure compliance with | |||
regulatory requirements. | |||
' | |||
In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter and | |||
its enclosures wil! be placed 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. Appendix A, Notice of Violation | |||
cc w/ encl: | |||
G. A. Hunger, Jr., Chairman, Nuclear Review Board and Director, Licensing | |||
T. Mitchell, Vice President, Peach Bottom Atomic Power Station | |||
G. Rainey, Senior Vice President, Nuclear Operations | |||
D. B. Fetters, Vice President, Nuclear Station Support | |||
T. Niessen, Director, Nuclear Quality Assurance | |||
C. D. Schaefer, External Operations - Delmarva Power & Light Co. | |||
G. Edwards, Plant Manager, Peach Bottom Atomic Power Station ; | |||
G. J. Lengyel, Manager, Experience Assessment l | |||
J. W. Durham, Sr., Senior Vice President and General Counsel | |||
P. MacFarland Goelz, Manager, Joint Generation, Atlantic Electric | |||
l | |||
._ . _ _ . . _ _ __ | |||
, | |||
s .. , | |||
* | |||
:. | |||
; | |||
Mr. D. M. Smith 3 ' | |||
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 i | |||
State of Maryland | |||
TMI - Alert (TMIA) l | |||
Distribution w/ encl: | |||
Region i Docket Room (with concurrences) | |||
Nuclear Safety Information Center (NSIC) | |||
i NRC Resident inspector , | |||
J | |||
PUBLIC | |||
K. Gallagher, DRP | |||
D. Screnci PAO | |||
i | |||
Distributio,1 w/ encl: (Via E-Mail) : | |||
W. Dean, OEDO | |||
J. Shea, NRR | |||
J. Stolz, PDI-2, NRR ! | |||
Inspection Program Branch, NRR (IPAS) | |||
R. Correia, NRR | |||
R. Frahm, Jr., NRR | |||
R. Zimmerman, ADPR, NRR | |||
F. Davis, OGC ! | |||
A. Nicosia, OGC | |||
J. Lieberman, OE (OEMAIL) | |||
D. Holody, EO, RI | |||
t | |||
DOCUMENT NAME: a:\peco.nov | |||
To receive a copy of this docu%t,icate in the boa: 'C' = Copy without attachtnent/ enclosure 'E' = Copy with attachment / enclosure | |||
*N* = No copy _f ) , , f | |||
ni;one fj ty lu ai:ose /g r3 y ni.ose ,/ ) je si;oss m l El ni:ons J j | |||
-- | |||
'5erice | |||
NAME WSchtrudti 'i ) PSwetiang j / WPascia$ L4 RBlough Y RCooper/(/VU | |||
oATE | |||
'' | |||
12/j)96 ' | |||
12d96 ' ' F /) 12//p06 s \ 12g796 12[y96 | |||
' | |||
, | |||
! | |||
n OFFICIAL RECORD COPY | |||
N' .d | |||
2)? | |||
g. | |||
1 | |||
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}} |
Latest revision as of 20:09, 8 August 2022
ML20138H772 | |
Person / Time | |
---|---|
Site: | Peach Bottom |
Issue date: | 12/27/1996 |
From: | Cooper R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
To: | Danni Smith PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
Shared Package | |
ML20138H777 | List: |
References | |
EA-96-264, EA-96-346, NUDOCS 9701060228 | |
Download: ML20138H772 (3) | |
See also: IR 05000277/1996006
Text
,
-
t >
.
1
l
<
December 27,1996
EA 96-264
EA 96-346 I
i
Mr. D. M. Smith, President l
PECO Nuclear !
Nuclear Group Headquarters
Correspondence Control Desk
P. O. Box 195
Wayne, Pennsylvania 19087-0195
l
SUBJECT: NOTICE OF VIOLATION
(NRC INSPECTION REPORT NO. 50-277/96-06 AND 50-278/96-06) ,
1
!
Dear Mr. Smith: j
i
This letter refers to the NRC inspection conducted from July 7,1996 to September 7,1996, l
'
at the Peach Bottom Atomic Power Station facility and to the apparent violation described in
the report associated with the emergency diesel generator and residual heat removal pump
interactions. The findings of the inspection were discussed with members of your staff during
an exit meeting on September 19,1996. In addition, the NRC inspection report was sent to ,
you with our letter, dated October 10,1996. On December 6,1996, a Predecisional !
Enforcement Conference was conducted with you and members of your staff to discuss the ;
related violation, its causes, and your corrective actions.
2
Based on the informe' an developed during the inspection, and the information provided during 4
the conference, or Violation of NRC requirements was identified. The violation is set forth !
in the enclosed f.otice of Violation. It involves the failure to verify the adequacy of the
modification der gn of Modification P-0231 prior to implementation as required by 10 CFR 50,
Appendix B, Criterion Ill, Design Control. Modification P-0231 provided for automatic
emergency diesel transfer from the droop to the isochronous mode of operation.
Modificatir,n P-0231 was first installed for two diesel generators in June 1995, but a full
understareding of its effects on other systems was not realized until June 1996, when
simulator runs were made. In cases where the plant response changes, the adequacy of the
new design must be verified, as required by 10 CFR Part 50, Appendix B, Criterion lil, and as
specified in ANSI N45.2.11-1974, to which you are committed. We are particularly concerned
that your staff did not understand all of the effects of the modification on the facility prior to
implementation of the modification. In your response to this letter, please pay particular
attention to what corrective actions you will put in place to ensure that the effects of future
modifications are understood prior to implementing them. {
}
During the predecisional enforcement conference we discussed at length the scenario that
involved an emergency diesel generator operating in the test mode and the effect of a
subsequent loss of coolant accident signal on the operability of the associated offsite power
source. It is our understanding that, until June 1996, your staff assumed that the emergency
N On O
9701060228 961227
PDR ADOCK 05000277 g*M
G PDR
f
s .
.
.
Mr. D. M. Smith 2
pumps would load onto the bus consistent with their assigned time delay sequences. During
the predecisional enforcement conference, your staff gave the position that,in consideration
of the actual starting sequence of the pumps, no specific evaluation would have been
necessary for this scenario because no credit was taken in the licensing basis for the diesel
generator bein0 on the bus. The point does not apply since you are required to understand
the effects of design changes on the overall facility design prior to implementation of the
modification.
it is also important to note that we recognize that your staff self-identified this issue during
simulator runs in June 1996, and subsequently, in your "PBAPS EDG Licensing Basis," dated
July 16,1996, your staff completed verification of the design of the modification. We will
review this document during a future inspection of your licensed activities.
You are required to respond to this letter and should follow the instructions specified in the
enclosed Notice when preparing your response. The NRC will use your response, in part to
determine whether further enforcement action is necessary to ensure compliance with
regulatory requirements.
'
In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter and
its enclosures wil! be placed 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. Appendix A, Notice of Violation
cc w/ encl:
G. A. Hunger, Jr., Chairman, Nuclear Review Board and Director, Licensing
T. Mitchell, Vice President, Peach Bottom Atomic Power Station
G. Rainey, Senior Vice President, Nuclear Operations
D. B. Fetters, Vice President, Nuclear Station Support
T. Niessen, Director, Nuclear Quality Assurance
C. D. Schaefer, External Operations - Delmarva Power & Light Co.
G. Edwards, Plant Manager, Peach Bottom Atomic Power Station ;
G. J. Lengyel, Manager, Experience Assessment l
J. W. Durham, Sr., Senior Vice President and General Counsel
P. MacFarland Goelz, Manager, Joint Generation, Atlantic Electric
l
._ . _ _ . . _ _ __
,
s .. ,
- .
Mr. D. M. Smith 3 '
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 i
State of Maryland
TMI - Alert (TMIA) l
Distribution w/ encl:
Region i Docket Room (with concurrences)
Nuclear Safety Information Center (NSIC)
i NRC Resident inspector ,
J
PUBLIC
K. Gallagher, DRP
D. Screnci PAO
i
Distributio,1 w/ encl: (Via E-Mail) :
W. Dean, OEDO
J. Shea, NRR
J. Stolz, PDI-2, NRR !
Inspection Program Branch, NRR (IPAS)
R. Correia, NRR
R. Frahm, Jr., NRR
R. Zimmerman, ADPR, NRR
F. Davis, OGC !
A. Nicosia, OGC
J. Lieberman, OE (OEMAIL)
D. Holody, EO, RI
t
DOCUMENT NAME: a:\peco.nov
To receive a copy of this docu%t,icate in the boa: 'C' = Copy without attachtnent/ enclosure 'E' = Copy with attachment / enclosure
- N* = No copy _f ) , , f
ni;one fj ty lu ai:ose /g r3 y ni.ose ,/ ) je si;oss m l El ni:ons J j
--
'5erice
NAME WSchtrudti 'i ) PSwetiang j / WPascia$ L4 RBlough Y RCooper/(/VU
oATE
12/j)96 '
12d96 ' ' F /) 12//p06 s \ 12g796 12[y96
'
,
!
n OFFICIAL RECORD COPY
N' .d
2)?
g.
1
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