ML20155F584
| ML20155F584 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 06/09/1988 |
| From: | Durr J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Mroczka E CONNECTICUT YANKEE ATOMIC POWER CO. |
| References | |
| NUDOCS 8806160433 | |
| Download: ML20155F584 (2) | |
See also: IR 05000213/1988001
Text
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JUN 0 91998
Docket No. 50-213
Connecticut Yankee Atomic Power Company
ATTN: Mr. E. J. Mroczka
Senior Vice President - Nuclear
Engineering and Operations Group
P. O. Box E70
Hartford, Connecticut 06141
Gentlemen:
Subject:
Inspection No. 50-213/88-01
This refers to your letter dated April 18, 1988, in response to our letter
dated March 21, 1988.
Thank you for informing us of the corrective and preventive actions documented
in your letter.
These actions will be examined during a future inspection of
your licensed program.
Your cooperation with us is appreciated.
Sincerely,
Orisir al sigr.cd EY 1
Jacque P. Durr, Chief
Engineering Branch
Division of Reactor Safety
cc:
0. B. Miller, Station Superintendent
D. O. Nordquist, Director of Quality Services
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R. M. Kacich, Manager, Generation Facilities Licensing
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W. D. Romberg, Vice President, Nuclear Operations
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Gerald Garfield, Esquire
Public Document Room (PDR)
local Public Document Room (LPDR)
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Nuclear Safety Information Center (NSIC)
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NRC Resident Inspector
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State of Connecticut
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OFFICIAL RECORD COPY
RL HN 88-01 - 0001.0.0
8806160433 080609
05/31/88
ADOCK 05000213
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Region I Docket Room (with concurrences)
Management Assistant, ORMA
Section Chief, DRP
W. Raymond, SRI, Millstone 1&2
A. Wang, LPM, NRR
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(203) 665-5000
April 18, 1988
Docket No. 50-213
A07129
Re:
Mr. Jacque
P.
Durt
Chief, Engineering Branch
Division of Reactor Safety
U.S.
Nuclear Regulatory Commission
475 Allendale Road
King of Prussia, PA
19406
Reference:
(1)
J.
P.
Durr letter to E.
J.
Mroczka, transmitting
Inspection No. 50-213/88-01, dated March 21,
1988.
Gentlemen:
Haddam Neck Plant
Response to Inspection Report No. 83-01
Reference (1) transmitted the results of Inspection No. 50-213/
88-01 which was conducted on January 11-21, 1988 of the Haddam
Neck Slant Inservice Test (IST) program.
During that inspection,
one N.olation of NRC regulations was identified related to a
failure to properly record a valve opening time as required by
the test procedure.
Connecticut Yankee Atomic Power Company
(CYAPCO) hereby provides its response to the identified
violation.
Requirement
Connecticut Yankee Atomic Power Company, Haddam Neck Plant,
Technical .,pecification 6.8,
"Procedures", requires that written
procedures and administrative policies shall be established,
implemented and maintained that meet the requirements and
recommendations of Section 5.1 and 5.3 of ANSI N18.7-1976 and
Appendix A of USNRC Regulatory Guide 1.33.
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Mr. Jacque P.
Durr
A07129/Paga 2
April 18, 1988
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Section 6.1.1 of Surveillance Procedure No. SUR 5.7-67,
"Inservice Inspection of Service Water Isolation Valves
SW-AOV-130, SW-A0V-8 and SW-AOV-9, Revision
8",
required
recording of the opening time for Service Water Valve SW-Aov-129.
Violation
contrary to the above, on January 12, 1988, the opening time for
Service Water Valve SW-A0V-129 was not recorded during the above
surveillance test.
This is a severity Level V Violation.
Root Cause
We have determined that this violation was the result of the
procedure being unclear regarding the format in which the data
were to be recorded.
The procedure provided a box containing the
acceptance criteria followed by another box in which the actual
stroke time measurement was to be recorded (see Attachment 1).
Below this was another larger box in which the operator acknowl-
edged obs9rvation of the valve actuating to the proper position
by circling the word SAT or UNSAT.
In other cases, valve stroke
times (e.g.,
closing times) were required to be recorded as a
separate line item, thus making it very unlikely that the
recording of the data would be overlooked.
The small size of the
stroke time data box as well as a misunderstanding on the part of
the operator that the SAT /UNSAT box also applied to the stroke
time measurement both contributed to the cause of this violation.
Corrective Action
CYAPCO acknowledges that during the performance of surveillance
procedure SUR 5.7-67, the non-licensed plant operators responsi-
ble for the conduct of the procedure failed to record the
measured opening time for valve SW-AOV-129.
The conduct of this
surveillance was at the time being observed by the NRC Staff and
a member of the plant engineering staff.
After it was pointed
out by the NRC Staff that the required data had not been
recorded, the plant operators were advised that all valve stroke
time measurements'were to be recorded on the procedure.
The
opening time for valve SW-AOV-129 as well as all subsequent
stroke time measurements were recorded as required.
It should be
noted that the procedure is not complete until all data have been
evaluated by the cognizant IST Engineer and reviewed by the
Engineering Supervisor.
If this error had not been identified
during the performance of the procedure, it would have been
discovered during the engineering evaluation.
Missing data would
have been obtained in a retest.
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Mr.
Jacque P.
Durr
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A07129/Page 3
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April 18, 1988
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Actions to Prevent Recurrence
As a corrective measure to prevent future violations, a new
format to clarify data recording has been developed and will be
implemented generically on all IST and other surveillance
procedures as part of the current station procedure improvement
program which is scheduled to be completed by the end of 1989.
If you have any questions related to the above, please feel free
to contact my staff directly.
Very truly yours,
CONNECTICUT YANKEE ATOMIC POWER COMPANY
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E.
J.
Mroczka
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Senior Vice President
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Vice President
Attachment
cc:
U.S. Nuclear Regulatory Commission
Attn:
Document Control Desk
D.C.
20555
A.
B.
Wang, NRC Project Manager, Haddam Neck Plant
J.
T. Shedlosky, Senior Resident Inspector, Haddam Neck Plant
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Docket No. 50-213
A07129
Attachment 1
Haddam Neck Plant
Procedure SUR 5.7-67, Rev. 8
Section 6.1.1
April 1988
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SUR 5.7-67
Rev. 8
APR 221987 l
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SUR57J
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4.0 PREREQUISITES
INITIALS
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4.1 Check whether the test is surveillance or retest
on Page 1.
Include the AWO number if applicable.
4.2 EG2A not operating when testing SW-A0V-129.
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4.3 EG2B not operating when testing SW-A0V-130.
4.4 Boron Recovery System shutdown when testing SW-A0V-8.
4.5 Spent Fuel. Pit Heat Exchanger can be inservice or
isolated when testing SW-A0V-9.
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4.6 A calibrated stopwatch is available to measure stroke
1
time.
Stopwatch Number
Calibration Due Date
- 4.7 SW-A0V-129, 130, 8 & 9 valves may be tested in accordance
with this procedure.*g
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4.8 Two (2) operators used to perfonn test.
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5.0 PRECAUTIONS
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5.1 Do not leave SW-A0V-129 and SW-A0V-130 open any
longer than necessary to perfonn test.
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5.2 Notify control room personnel prior to perfonning
test.
6.0 PROCEDURE
6.1 Complete test for SW-A0V-129 as follows:
6.1.1
Open SW-A0V-129. Measure opening time from
placing raw water control switch on EG2A
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control panel in the manual position until
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valve is locally observed to be fully open.
Acceptance Criteria
Test Results
30 sec, to open, or less
see
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Valve exercised to open
Sat /Unsat
position as indicated by
local observation
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Page 2 of 9
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