ML20198J054
| ML20198J054 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 09/17/1997 |
| From: | Grant G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Tulon T COMMONWEALTH EDISON CO. |
| References | |
| 50-454-97-09, 50-454-97-9, 50-455-97-09, 50-455-97-9, 50-456-97-09, 50-456-97-9, 50-457-97-09, 50-457-97-9, EA-97-265, NUDOCS 9709250091 | |
| Download: ML20198J054 (29) | |
See also: IR 05000454/1997009
Text
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NUCLEAR RECULATORY COMZlSSION
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REGION 111
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Septmber 17, 1997
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EA 97 265
Mr. T. Tulon
Site Vice President
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Braldwood Station
Cornmonwealth Edison Company
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RR #1, Box 84
Braceville, IL 60407
SUBJECT: NRC PREDECISIONAL ENFORCEMENT CONFERENCE REPORT
Dear Mr. Tulon:
This refers to the combined Byron /Braidwood Predocisional Enforcement Conference
conducted by Mr. James L. Caldwell, Deputy Regional Administrator, and other members
f
of the NRC Region lll and headquarters staff on September 11,1997. The subject of this
conference was the apparent violations at Byron and Braidwood Stativ..s. identified in
NRC Inspection Report Nos. 50 454/97009(DRP): 50 455/97009(DRP); and
50 456/97009(DRP) 50-457/97009(DRP), concerning emergency core cooling system
venting. We have enclosed a partiallist of attendees (Enclosure 1), a copy of the draft
proposed violation related to Braidwood that was provided to you at the conference
(Enclosure 2), and a copy of the handout provided during the conference (Enclosure 3).
You will be notified by separate correspondcnce of our decision regarding the enforcement
action based on the infortnation presented and discussed at the predecisional enforcement
conference. No response is required until you are notified of the proposed enforcement
action,
in accordance with 10 CFR 2.790 of the Commission's regulations, a copy of this letter
and the enclosed report will be placed in the NRC Public Document Room.
"
9709250091 970917
ADOCK 05000454
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T. Tulon
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We will gladly discuss any questions you have concerning this Predecisional Enforcement
Conference.
Sincerely,
/s/ Marc L. Dapas for
Geoffrey E. Grant, Director
Division of Reactor Projects
<
Docket Nos. 50 456: 50 457
Licenses Nos. NPF 72; NPF 77
Enclosures:
As Stated
cc w/o encls:
R. J. Manning, Executive
Vice President, Generation
M. Wallace, Senior Vice
President, Corporate Services
,
H. G. Stanley, Vice President
PWR Operations
D. A. Sager, Vice President,
Generation Support
D. Farrar, Nuclear Regulatory
Services Manager
1. Johnson, Licensing
Operations Manager
T. Simpkin, Regulatory
Assurance Supervisor
Braldwood Station Manager
cc w/encls:
Document Control Desk Licensing
Richard Hubbard
Nathan Schloss, Economist
Office of the Attorney General
State Liaison Officer
Chairman, Illinois Commerce
Commission
Distribution:
Docket File w/encls
SRI Braidwood w/encls
DRP w/encla
OC/LFDCB w/encls
Project Mgr., NRR w/encls
TSS w/encls
PUBLIC IE 01 w/encls
J. Lieberman, OE w/encls
DRS (2) w/encls
A. Beach w/encls
J. Goldberg, OGC w/encls
Rlli PRR w/encls
Deputy RA w/encls
R. Zimmerman, NRR w/encls
RAC1 (E Mail)
Rill Enf. Coord, w/encls
CAA1 (E Mail)
DOCDESK (E Mail)
DOCUMENT NAME: G:\\BRAl\\ BRA 97009.ENF
SEE PREVIOUS CONCURRENCES
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OFFICIAL RECORD COPY
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T. Tulon
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We will gladly discuss any questions you have concerning this Predecisional Enforcement
Conference.
Sincerely,
Geoffrey E. Grant, Director
Divialen of Reactor Projects
Docket Nos. 50 456; 50 457
Licenses Nos. NPF 72: NPF 77
Enclosures:
As Stated
cc w/o encl:
R. J. Manning, Executive
Vice President, Generation
M. Wallace, Senior Vice
President, Corporate Services
H. G. Stanley, Vice President
PWR Operations
D. A. Sager, Vice President,
Generation Support
D. Farrar, Nuclear Regulatory
Services Manager
1. Johnson, Licensing
Operations Manager
T. Simpkin, Regulatory
Assurance Supervisor
Braldwood Station Manager
(See attached continued distribution)
DOCUMENT NAME: G:\\BRAl.lR\\ BRA 97009.ENF
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DATE
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09/th/97
09/4/97
07/'/97
09/ /97
OFFICIAL RECORD COPY
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ENCLOSURE 1
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Partial List of Persons Present at Conference
Commonwealth Edison Corppany (Comed)
E. Stanley, Vice President - PWR
D. Sager, Vice President Generation Support
K. Groesser, Site Vice President Byron Station
T. Tulon, Site Vice President Braidwood Station
W. Subalusky, Site Vice Preside..t LaSalle Station
K. Kofron, Plant Manager Lyron Station
R. Wegner, Operations Manager Byron Station
T. Gierich, Operations Manager Braidwood Station
- D. Wozniak, Engineerire Manager Byron Station
D. Brindle, Regulatory Assurance Supervisor Byron Station
T. Simpkin, Regulatory Assurance Supervisor Braidwood Station
. l. Johnson, Licensing Operations Manager
U. S. Nuclear Raoulatory Commlanlon
J. Caldwell, Deputy Regional Administrator, Rill-
M. Depas, Acting Deputy Director, D,ivision of Reactor Projects, Rill
R. Capra, Director, Project Directorate ill 2, NRR
R. Lanksbury, Chief, Reactor Pro}ects Branch 3
B. Borson, Regional Counsel
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H. Clay'on, Enforcement Officer
S. Burgess, Senior Resident inspector, Byron Station
C. Phillips, Senior Resident inspector, Braidwood Station -
T. Tongue, Project Engineer
N. Hilton, Resident inspector, Byron Station
R. Burrows, Reactor Engineer
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DRAFT
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The apparent violations discussed in this predecisional enforcement conference are subject
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to further review and are sub}ect to change prior to any resulting enforcement action.
ENCLOSURE 2
BRAIDWOOD NUCLEAR POWER STATION
PROPOSED VIOLATION . INSPECTION REPORT 9700g
Technical Specification 3.5.2 requires that two independent emergency core cooling
system (ECCS) subsystems be operable with each subsystem comprised of a) one operable
centrifugal charging pump, b) one operable safety injection pump, c) one operable residual
heat removal (RHR) heat exchanger, d) one operable RHR pump, and, e) an operable flow
path capable of taking suction from the refueling water storage tank on a safety injection
signal and automatic opening of the containment sump suction valves.
Technical Specification Surveillance 4.5.2.b(1) requires that each ECCS subsystem be
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demonstrated operable at least once per 31 days by venting the ECCS pump casings and
discharge piping high points outside of containment.
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Contrary to the above the inspectors identified that since commercial operation began in
1987 and 1988, respectively, for the Unit 1 and Unit ? and continuing until May 1997, a
ECCS sub system consisting of the centrifugal charbag (CV) pump had not been
demonstrated operable at least once per 31 de'c by venting the casing and the CV high
point vents outside containment when the uni; o as in Modes 1,2, and 3.
The apparent violations discussed in this predecisional enforcement conference are subject
to further review and are subject to change prior to any resulting enforcement action.
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ERCLOSURE 3
BYRON /BRAIDWOOD NUCLEAR POWER
STATIONS
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ECCS VENTING
and
SLAVE RELAY TESTING
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PRE-DECISIONAL
ENFORCEMENT CONFERENCE
September 11,1997
NRC Region III
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AGKNDA
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+ OPENING REMARKS
K. Graesser
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+ CV VENTING
R. Wegner
+ RH VF;NTING,
D. Wozniak
SI PUMP SURVEILLANCE,
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SLAVE RELAY TESTING
+ CLOSING REMARKS
G. Stanley
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OPEMNG REMARKS
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+ Agree with the inspection findings supporting the
apparent violations
+ NRC's message is clear - literal compliance with
Technical Specifications
+ Byron and Braidwood strive to comply with all
regulatory requirements
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ECCS VENTING
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+ ISSUES
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+ POSITION
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+ ROOT CAUSE
+ SAFETY SIGNIFICANCE
+ CORRECTIVE ACTIONS
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ECCS VKNTING ISSUES
+ Failure to be in compliance with the Technical
Saecifications
Byron and Braidwood
+ CV Venting
Pump casings
CV High points
Byron
+ RH Venting
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+ SI Pump Surveillance Procedure
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CV VKNTING
+ Issue:
Fai;.ure to vent CV system accorc.ing
to Technica Saecification requirements
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+ Position
Compliance issue was evaluated previously
Determination of compliance
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+ Self-venting pump
+ System always under pressure
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ROOT CAUSE
Faulty evaluation that the continuous venting feature
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met t;ae Technical Specification requirements
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SAFETY SIGMFICANCE
+ Minimal safety significance
Weekly / Monthly UT surveillance has revealed no voids
+ Minima imaact on CV system function capaaiLity
Fully capable of performing its intended design function,
including design basis accident mitigation
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CORRECTIVE ACTIONS
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+ Actions to prevent recurrence
Ultrasonic testing inspection of vulnerable areas in CV
system
+ Unit 1 and Unit 2 - monthly testing
Revised procedure / schedule as appropriate (By - 06/97,
Biv - 7/97)
Reviesv of selected Technical Specification surveillances to
verify literal compliance (08/29/97)
Distributed Station Manager letters (09/10/97)
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Plant Operational Review Committee (PORC), involvement
(11/07/97)
Effectiveness Reviews (09/11/98)
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CORRECTIVE ACTIONS - cunt.
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+ Actions to achieve compliance (08/13/97)
Appropriate Licensing submittals were made
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RH DISCHARGE VENT'
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+ Issue:
Failure to vent Unit : R3 cischarge aiping
vent 1RH027 per Tec mical Specifications
+ Root Cause
Deficient surveillance procedure
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SAFETY SIGMFICANCE
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Vinima safety signi:~1cance
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Minimal impact on RH system function capabi:.ity
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Fully capable of performing its intended design function,
including design basis accident mitigation
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CORRECTIVE ACTIONS
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+ Revised Unit 1 Monthly Venting Surveillance
procec ure to incoraorate
RH027 (06/03/97)
+ Reviewec. ECCS isometric crawings, verifying all
aig 1 point vent valves are incluc.ed in survei . lance
procec ure (06/08/97)
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SI PUMP SURVEILLANCE
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+ Issue:
Inac equate SI pump venting
surveillance procec ure (1/2 BOS 5.2.b-1)
+ Root Cause
Procedure was inadequate in that all potential vent paths were
not identified
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SAFETY SIG31FICANCE
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Minima
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Pump venting capability was maintained
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CORRECTIVE ACTIONS
Revisec 1/2 BOS 5.2.a-1, "ECCS Venting and
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Valve A;;ignment Month y Surveillance," to provic e
guic elines to perform venting ay alternate means
(06/03/97)
Reviewed other ECCS pump configurations for
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pump venting capabilities (06/08/97)
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SLAVE RELAY TESTING
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ISSUES
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SEQUENCE OF EVENTS
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ROOT CAUSE
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SAFETY SIGNIFICANCE
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CORRECTIVE ACTIONS
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ISSUES
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+ Failure to perform CV letc own isolation valve s: Lave
re ay test per Technica Specifications
+ Failure to perform CV letdown orifice isolation
va.ve s_ ave re_ay test ger Tecanical Speci:ications
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SEQUENCE OF EVENTS
+ Pre-1990 - Va ves stroked per Technical Specifications
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_990 - Westing louse letter recommenc ec not to stroxe
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valves due to thermal transient issue
Jumper temporarily used to prevent stroking valves
+ Permanent ootions to correct t:ae issue consic.erec :
Modification to prevent stroking valves
Technical Specification change to extend the surveillance
frequency
+ Technical Specification change chosen
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SEQUENCE OF EVENTS - cont.
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In Marc a 1996, a jumper :Te_1 off causing a etc own
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iso ation (LER 96-001)
Safety Review Committee review c uestionec t:1e use 0:i
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tae jumper
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Tec anica. Speci ~1 cation Slave Relay Test c.efinition
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review determinec.:
Jumper installation and fuse removal did not meet the Technical
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Specification surveillance requirements
Slave relays were declared inoperable
S; ave re..ay survei; ances e aangec. to strole va_ves anc
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t aen per:Pormec. to meet the Technica: Specification
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ROOT CAUSE
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Inac equate Tec mica. Specification surveillance
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Inac ec uate on-site reviews
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-SIFETY SIG31FICANCE
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Minimal safety significance
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Slave relays / additional equipment tested on quarterly
basis
Functionec. on demand
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CORRECTIVE ACTIONS
+ Per: forming reviews 0: Pal; slave relay survei: .ance
arocec.ures (: 1/07/97)
+ Eva uating moci:~1 cation to test components
quarterly (12/05/97)
+ Review of se.ectec. Technica Specification
surveillances :Por litera comp..iance (08/29/97)
+ Plant O oerational Review Committee (PORC) is in
1 ace (: :./07/97)
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CLOSING REVIARKS
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+ Focus on improving
+ Ensure compliance
+ Common approach
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