05000446/LER-1999-001, :on 981226,identified That TS Surveillance for Containment Integrity Verification Was Not Performed.Caused by Personnel Error.Required Surveillance Was Performed & Applicable Procedures Were Revised.With
| ML20199L187 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 01/19/1999 |
| From: | Goodwin D, Terry C, Walker R TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LER-99-001, LER-99-1, TXX-99004, NUDOCS 9901270150 | |
| Download: ML20199L187 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i) |
| 4461999001R00 - NRC Website | |
text
1
" j<
.x -
M==
~
Z Log # TXX-99004 7UELECTRIC File # 10200 Ref. # 10CFR50.73(a)(2)(i) c. tasse wrvy'.
s i., n. r u,
' & PrincipalNaclear Opcer January 19,1999 i
I U. S. Nuclear Regulatory Commission Attn: Document Control Desk
]
~ Washington, DC 20555 l
t SUBJECT:'
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)-UNIT 2
}
DOCKET NOS. 50-446
.i CONDITIONS PROHIBITED BY TECHNICAL SPECIFICATIONS l
LICENSEE EVENT REPORT 446/99-001-00 Enclosed is Licensee Event Report (LER) 99-001-00 for Comanche Peak Steam Electric Station Unit 2, " Technical Specification Surveillance for Containment Integrity Verification Was Not Performed on a Penetration Due to Personnel Error."
This communication contains no new licensing basis commitments regarding CPSES Unit 2.
e Sincerely, G $.#
C. L. Terry By:[ AWL, b.
Roger 5. Walker Regulatory Affairs Manager OB:ob -
O Enclosure
' cc:
Mr; E. W. Merschoff, Region IV Mr. J.1. Tapia, Region IV Resident inspectors, CPSES O
'~
9901270150 990119'
/
PDR ADOCK 05000 8
PDR g COMANCHE PEAK SILAM ELECTRIC STATION P.o. Box 1002 Glen Rose. Texas 76043-1002 i-
Enclosura to TXX-99004 groRu see u.8. NUCLEAR REGULATORY COMMISSON APPROVED 3190 0104 ESTIMATED BURDEN PER RESPONSE TO COMPLv wtTH TH15 MANDATORY LICENSEE EVENT REPORT (LER)
%"a"S' E'o'TO # E# 5'#oc'EP WE7'E"t (S e reverse for required number of Ea=Y=UcoTno ENIoEaYr aaa"ca5'IEsSSE 9
digits / characters for each block) hh (PamEcNo For/ic%E=aTEr a*so Facsety Nome (1)
Docket Number (2)
Page (3) l COMANCHE PEAK STEAM ELECTRIC STATION UNIT 2 05000446 01 0F 04 i
T6tle(4)
TECHNICAL SPECIFICATION SURVEILLANCE FOR CONTAINMENT INTEGRITY VERIFICATION WAS NOT PERFORMED ON A PENETRATION DUE TO PERSONNEL ERROR i
Event Date ((5)
LER Number (6)
Report Date (7)
Otner F acmues invceveo (8)
Month Day Year Year Sequenhal Revisson Montn Day Year f actly Name h~"-'
na m*= 's
""'"b"
""'"b" C'SES UNIT 1 0
5 0
0 0
4 4
5 1l2 2l6 9l8 9l9 0l0l1
- - 0l0 0
1 1l9 9l9 N/A 0
5 0
0 0
Cg e,,,,
Tum renort na mu:.. _:: : rwarnunn to the tantar-mansa ni 10 CFR A N:e one or mrsmii11)
Mode (9)
]
202201 (b) 202203 (a)(2)(v) 3., 50 73 (a)(2)(t) 5013(a)(2)(ve) p,
,, 20.2203 (a)(1) 20.2203 (a)(3) 0)
,, 50 73 (a)(2)(ii) l 202203 (a)(2)oi)
,,,,, 202203 (a)(3)(ii) 5013(a)(2)(m)
, 5013 (a)(2)(x) 20.2203 ra)(2) 0) g 100 20.2203 (a)(2) Die) 202203 (a)(4) 5013 (a)(2) ov) 7311
,,,, OTHER
- gio, 20 2203 (a)(2) ev) 50.36 (c)(1) 5013(a)(2)(v)
Specify in Abstract below i
60 36 fe)(2) 60 73 (a)(2)(vh) or in NRC Form 366A ucensee Contact For This LER (12)
Name Teiepnone NumDer (incluoe Area Cooe)
David A. Goodwin - Operations Support Manager (254)897-0815 Compecto One Lane For Each Component Fanure Descrineo m This f epore (13)
Cause
System Component Manufacturer Reportab4e
Cause
bystem Component Manufacturer Reportatue To NPRDS To NPRIX3 N
Q Suppeementat Repon Expecieo (14l Month Day Year EXPECTED YE'S.
X NO SUBMISSION I
l l
(W wes. comoisted F.XPFCTFD SUBMISSON DATF)
DATE (16) l l
l ABSTRACT (Umit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16)
On December 26,1998, while performing primary containment integrity verification, Operations Plant Equipment Operator (PEO) (utility, non-licensed) identified that a penetration used for Comanche Peak Steam Electric Station (CPSES) Unit 2 integrated leak rate testing was not listed on the verification data sheet. The PEO performed the required verification and notified Operations shift management (utility, licensed) about the procedure anomaly. On December 28,1998, it was concluded that a violation of CPSES Technical Specifications had transpired.
TU Electric's evaluation of the event deemed that an adequate design modification impact review was not performed by the responsible organization. Immediate corrective action was to perform the required surveillance. The applicable procedures have been revised to incorporate the penetration in the verification data sheet.
Ericlosura to TXX-99004 SUMMARY OF THE EVENT, INCLUDING DATES AND APPROXIMATE TIMES CPSES Technical Specification (TS) @ 3.6.1.1, requires that, primary containment integrity be maintained in Modes 1,2,3, and 4. Moreover, TS Q 4.6.1.1.a requires that the primary containment integrity be demonstrated at least once per 31 days by verifying that all penetrations
- not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except as provided in Table 2.1.1 of the CPSES Technical Requirements Manual.
Except valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked, sealed or otherwise secured in the closed position. These penetrations shall be verified closed during each COLD l
SHUTDOWN except that such verification need not be performed more often than l
once per 92 days....
i F
Endlosuro to TXX-99004 NRQFORM 366A U S NUCLEAR REGULATORY COMMISSION pm)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION "Cf rumir.m.ni on.i w
g,_
9 9
o o
1 COMANCHE PEAK STEAM ELECTRIC STATION UNIT 2 05000446 OF 03 04 m,_.
.,_.m.. _. _
RC,-,
,on On December 26,1998, while performing the verifications pursuant to the requirements of the aforementioned TS sections. A Plant Equipment Operator (PEO) (utility, non-licensed) identified that a penetration used for CPSES Unit 2 integrated leak rate testing was not iisted on the verification data sheet. The PEO performed the required verification and notified Operations shift management (utility, licensed) about the procedure anomaly. On December 28,1998, it was concluded that a violation of CPSES Technical Specifications had transpired.
E.
THE METHOD OF DISCOVERY OF EACH COMPONENT OR SYSTEM FAILURE, OR PROCEDURAL CR PERSONNEL ERROR Plant Equipment Operator while performing his assigned surveillance identified that the Unit 2 penetration was not listed on the verification data.
II.
ANALYSIS OF 5 EVENT A.
SAFE 1 f SYSTEM RESPONSES THAT OCCURRED Not applicable - no safety system responses occurred as a result of this event.
B.
DURATION OF SAFETY SYSTEM TRAIN INOPERABILITY Not applicable - no safety system train was deemed inoperable.
j C.
SAFETY CONSEQUENCES AND IMPLICATIONS OF THE EVENT CPSES Technical Specification (TS) 3.6.1.1 surveillance requirements provides reasonable assurance that the release of radioactive material from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the safety analysis. Following installation of the test connection during the Unit 2 third refueling outage around or about November 8,1997, and the successful performance of the local leak rate test, the test connection and the penetration bolted flanges (both inside and outside the containment) were verified, capped and closed. Adequate confidence l
exists that test connection has not been removed or opened for reasons other than the test performed during the Unit 2 third refueling outage. It is therefore concluded that the containment integrity was not compromised, and the condition did not adversely affect the safe operation of CPSES Unit 2 or the health and safety of the public.
t I
. -.. ~ - -
E6 closure to TXX-99004 NRQ FORM Sti6A U S NUCLEAR REGULATORY COMMISSION (443)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION Tg",,"
recay Neme m onu 9
9
. 0YI O
O OF COMANCIIE PEAK STEAM ELECTRIC STATION UNIT 2 05000446 o4 g
Tact (# more spece is required, use addmonal copies of NRC Form 366A) (17) 111.
CAUSE OF THE EVENT
During November 1997, a design modification was implemented to install a test connection and the two flanges to allow for depressurization of CPSES Unit 2 containment during the integrated Leak Rate Testing and for cable feed through during normal outage activities. An interdisciplinary review was performed by the operations department. However, this particular test connection was not incorporated in the primary containment integrity verification data sheet.
TU Electric's evaluation of the event deemed that an adequate design modification impact review was not performed by the responsible organization.
IV.
CORRECTIVE ACTIONS
Immediate corrective action was to perform the required surveillance. The applicable procedures have been revised to incorporate the penetration in the verification data sheet.
V.
PREVIOUS SIMILAR EVENTS
There has been previous similar events that pertain to missed surveillances. However, the causes for those events were sufficiently different than this event such that the corrective actions would not have prevented this event.
l 1
i i
i d
d