05000213/LER-1998-001, :on 980409,seismic Monitor Sp Was Not in Compliance W/Ts.Caused by Inadequate Engineering Review. Submitted Proposed License Amend to Correct Issue
| ML20247E411 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 05/07/1998 |
| From: | Bouchard G, Haseltine J, Sickles K CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| CY-98-048, CY-98-48, LER-98-001, LER-98-1, NUDOCS 9805180336 | |
| Download: ML20247E411 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2)(ii) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(1) |
| 2131998001R00 - NRC Website | |
text
(
CONNECTICUT YANKEE ATOMIC POWER COMPANY i
l HADDAM NECK PLANT 362 INJUN HOLLOW ROAD e EAST HAMPTON, CT 06424-3099 l
May 7, 1998 CY-98-048 Re: 10CFR50.73 (a) (2) (i) (B)
U.
S. Nuclear Regulatory Commission j
Attention:
Document Control Desk i
Washington, DC 20555 j
Reference:
Facility Operating License No. DPR-61 I
Docket No. 50-213 Reportable Occurrence LER 50-213/1998-001-00 This letter forwards Licensee Event Report 1998-001-00, required to be submitted, pursuant to the requirements of the j
l Haddam Neck Plant's Technical Specifications.
i l
I Very truly yours, For: G. H. Bouchard Un'
're tor
/
By:
Haseltine Engineering Director GHB/rww
Attachment:
LER 50-213/1998-001-00 l
cc:
Mr. H.
J. Miller Regional Administrator, Region I 475 Allendale Road King of Prussia, PA 19406 t
Mr. William J.
Raymond Sr. Resident Inspector Haddam Neck
{
46 f
we-s nv r+
/
1 9805180336 980507 PDR ADOCK 05000213 S
PDR L______-__--
e op
?
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED SY OMS NO.3150-0104 g.g$)
EXPIRES 04/30/98 I'N O A'T COL E710 E8W o S
EPC TED L N
L'e"'?o^"40"## "Eia!Po '"sn'"?.*Vo"f.ca'o ^=!:
LICENSEE EVENT REPORT (LER) 15; = '<'f '"* g fa=^/ g g ; 4 g gs g o",am n<,% 3 ; g " gc U
$N'EMa*0af'?aI"r'Eo'li Es"! Elfs"wV81"oI"?!EsW.'""
(See reverse for required number Of digits / characters for each block)
FAClWTY NAME (1)
DOCKET NUMBER (2)
PAGE (3)
Haddam Neck 05000213 1 of 4 f
TITLE 14)
Seismic Monitor Surveillance Procedure not in Compliance with Technical Specifications EVENT DATE (6)
LER NUMBER (6)
REPORT DATE (7)
OTHER FACILITIES INVOLVED (8)
MONTH DAY YEAR YEAR SEQUENTIAL REVISION MONTH DAY YEAR FAclWTY NAME DOCKET NUMBER NUMBER 05000 04 09 1998 1998 001 00 05 07 1998 l
05000
[
OPERATING N
THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR 5: (Check one or more) (11)
MOM M 20.2201(b) 20.2203(a)(2)(v)
X 60 73(=>(2)(i) 50.73(a)(2)(viii)
POWER 20.2203(a)(1) 20.2203(a)(3)(i) 50.73(a)(2)(ii) 50.73(a)(2)(x)
LEVEL 00) 000 20.2203(a)(2Hi>
20.2203(a)(3)(ii) 50.73(a)(2)(iii) 73.71
"(T N % J 20.2203(a)(2)(ii) 20.2203(a)(4) 50.73(a)(2)(iv)
OTHER MWh, Mb % iMD,
.g 9
20.2203(aH2)(iii) 50.36(c)(1) 50.73(a)(2)(v)
Specify in Abstract below f
hQhgg;g gfNdb D/
i 20.2203(a)(2)(iv) 50.36(c)(2) 50.73(a)(2)(vii)
LICENSEE CONTACT FOR THIS LER (12) l NAME TELEPHONE NUMBER (inclurte Area Code) l Keith Sickles, Engineering Supervisor (860)267-3924 l
l COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
CAUSE
SYSTEM COMPONENT MANUFACTURER REPORTABLE
..h ?
CAUSE
SYSTEM COMPONENT MANUFACTURER REPORTABLE TO NPRDS q[$'
TO NPRDS t
cf
- ~
l t
l
%j(
V Y
SUPPLEMENTAL REPORT EXPECTED (14)
EXPECTED MONTH DAY YEAR SUBMISSION y NO YES (If yes, complete EXPECTED SUBMISSION DATE).
ABSTRACT (Limit to 1400 spaces, i.e.,
approximately 15 single-spaced typewritten lines)
(16)
On April 9, 1998, with the plant permanently shutdown and defueled, it was identified that past surveillance of the seismic monitoring system, performed in accordance with approved plant procedures, did not fully comply with the testing requirements as delineated in the H ddam Neck Plant's Technical Specifications, Section 4.3.3.3.1.
Since implementation of License Amendment 125, the triaxial servo accelerometer and the response spectrum analyzer hr.d not received a CHANNEL CALIBRATION or an ANALOG CHANNEL OPERATIONAL TEST as defined by the technical specifications. The cause of the event was an inadequate engineering review of i
tha definition of CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST as it relates to ths components that comprise the seismic monitoring system.
The corrective action for the inoperable seismic monitor will be to submit a proposed license amendment to correct this issue.
The seismic monitoring system was out of service at the time that the discrepancy was discovered and will remain out of service until a proposed license amendment is submitted by CYAPCO, and approved by the NRC.
NRC FORM 366 (4 95)
l
'F
- U.S. NUCLEAR REGULATORY COMMISSION (Ji-96)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME (1)
DOCKET NUMBER (2)
LER NUMBER (6)
PAGE (3)
YEAR SEQUENTIAL REVISION Haddam Neck NUMBER NUMBER 001 00 2 of 4 05000213 1998 TEXT filmore space is required. use additional copies of NRC Form 366A) (11l
BACKGROUND INFORMATION
On July 8, 1997, surveillance testing of the seismic monitoring system instrumentation provided unsatisfactory results, in that data was not being reproduced due to the ra:ponse spectrum analyzer being inoperable. Connecticut Yankee Atomic Power Company (CYAPCO), on July 8, 1997, declared the seismic monitoring system inoperable. On August 14, 1997, CYAPCO submitted a special report to the NRC in accordance with Technical Specifications 3.3.3.3.a and 6.9.2 outlining the cause of the malfunction and tha plans for restoring the system to an OPERABLE status, since repairs to the seismic monitoring system would exceed 30 days.
On April 9, 1998, with the plant permanently shutdown and defueled, it was identified that past surveillance of the seismic monitoring system did not fully comply with the testing requirements as delineated in the Haddam Neck Plant's Technical Specifications, Ssction 4.3.3.3.1.
CYAPCO has identified that since implementation of License Am:ndment 125, which was approved by the NRC on April 26, 1990, the triaxial servo accelerometer and the response spectrum analyzer had not received a CHANNEL CALIBRATION or an ANALOG CHANNEL OPERATIONAL TEST as defined by the technical specifications. This technical specification did not exist prior to License Amendment 125.
Tcble 4.3-4 of the Technical Specifications requires a semi-annual ANALOG CHANNEL OPERATIONAL TEST and a 18 month CHANNEL CALIBRATION of the seismic monitoring system which is accomplished via surveillance procedure SUR 5.2-67.
Tha ANALOG CHANNEL OPERATIONAL TEST as defined by technical specifications includes
"... adjustments, as necessary, of the alarm, interlock and/or Trip Setpoints such that tha Setpoints are within the required range and accuracy." Additionally, the CHANNEL CALIBRATION as defined by the technical specifications requires that "... adjustment, as nscessary, of the channel such that it responds within the required range and accuracy to known values of input."
Tha testing that had been previously performed did not verify that the triaxial servo accelerometer or the response spectrum analyzer responded within the required range and j
cecuracy of known input values, j
EVENT DESCRIPTION
Tha seismic monitoring system was declared inoperable on July 8, 1997.
The corrective sction to restore the system to an operable status was the replacement of the seismic l
monitoring system. This new equipment has been installed. As part of the modification it was necessary to revise the existing surveillance procedures to reflect the newly installed equipment. During the revision of procedure SUR 5.2-67, a thorough engineering review identified that the surveillance procedure would not actually test tha new system as described in the Technical Specifications. Further investigations led CYAPCO to the conclusion that the previous procedure was also inadequate as it NmC FORM 366A (4-95)
f c
r
.U.S. NUCLEAR RE;ULATORY COMMISSION
(&95)
- - LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME (1)
DOCKET NUMBER (2)
LER NUMBER (6)
PAGE (3)
YEAR SEQUENTIAL REVISION Haddam Neck NUMBER NUMBER 05000213 1998 001 00 3 of 4 1 EXT (11more space is required. use additional copies of NRC Form 366A) iill portained to the testing of the seismic monitoring system, which resulted in the historical failure to follow technical specifications.
On April 15, 1998, it was determined that from when the testhg requirements were first included in the technical specifications as part of License Amendment 125, which was cpproved on April 26, 1990, until the system was declared inoperable on July 8,
- 1997, tha seismic monitoring system surveillance testing was not performed as defined in the technical specifications. This was based on the fact that the triaxial servo accelerometer and the response spectrum analyzer had not received a CHANNEL CALIBRATION or an ANALOG CHANNEL OPERATIONAL TEST as defined by the Technical Specifications.
CAUSE OF EVENT
The cause of the event was an inadequate engineering review of the definition of CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST as it related to each of the components for the seismic monitoring system. The technical specification, as written, required surveillance to be performed that were not feasible for the installed units.
Specifically, the components could not be tested to the measurement ranges indicated in Tschnical Specification 3.3-5, and adjustments could not be made to the accelerometer (SSA-302), or analyzer (RSA-50).
It appears that the surveillance testing requirements were entered into the Technical Specifications in a fashion consistent with what was done for other instrumentation under the standard format for technical specifications for Westinghouse plants without a thorough engineering review.
SAFETY ASSESSMENT
This condition is reportable under 10CFR50.73 (a) (2) (1) (B) as a condition prohibited by.
plcnt technical specifications since surveillance required to be performed by the technical specifications were never properly performed. Therefore, the seismic monitoring system could not have been declared OPERABLE.
Since the new system has not been declared OPERABLE, the deportability of this issue partains to a historical perspective. Two of the four components did not receive a CHANNEL CALIBRATION or an ANALOG CHANNEL OPERATIONAL TEST as defined by the Technical Specifications since License Amendment 125 was approved by the NRC. However, system functionality was considered to have been accomplished since the testing that was successfully performed was in accordance with the procedure. The procedure used was I
dsveloped in accordance with manufacture's recommendations and meets accepted industry stcndards. The successful testing that was done is the basis of CYAPCO's conclusion that the seismic monitoring system was functional since 1990.
If a seismic event had occurred, CYAPCO believes that the seismic monitoring system would have functioned properly. However, in the unlikely event that the seismic
]
j monitoring system would not have functioned, a CYAPCO abnormal operating procedure j
l l
9<
- U.S. NUCLEAR REIULATORY COMMISSION l
LICENSEE EVENT REPORT (LER)
)
l TEXT CONTINUATION i
~
l FACILITY NAME (1)
DOCKET NUMBER (2)
LER NUMBER (6)
PAGE (3)
YEAR SEQUENTIAL REVISION Haddam Neck NUMBER NUMBER 00 4 of 4 05000213 1998 001 TEXT (if more space is required, use additional copies of NRC Form 366A) (11)
(AOP 3. 2-5) would direct the operators to verify the occurrence and magnitude of an esrthquake with the Millstone Station or with the Weston Observatory, given any evidence of such event. Based on the above, the safety significance of this event is i
judged to be low.
CORRECTIVE ACTION
Thn corrective action that will be taken by CYAPCO to restore the seismic monitoring system to an OPERABLE status will be to submit a proposed license amendment.
CYAPCO will submit the proposed license amendment to the NRC by July 1, 1998. The seismic monitoring system will remain inoperable until the technical specification change is approved by the NRC. With regard to the inadequate engineering review that was parformed, significant enhancements have been incorporated into the design change process and technical specification change process which should prevent this event from recurring.
ADDITIONAL INFORMATION
Ths following are commitments made within this report. All other statements are for information only.
CY-98-048-01 A proposed modification to the Haddam Neck Plant's technical specifications will be submitted to the NRC by July 1, 1998.
PREVIOUS SIMILAR EVENTS
LER 97-015-00 This LER discussed not performing functional terting of the i
radiation monitoring system as required by tho technical specifications.
i il