IR 05000293/1990002
| ML20006F258 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 02/07/1990 |
| From: | Eapen P, Joe Golla NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20006F256 | List: |
| References | |
| 50-293-90-02, 50-293-90-2, GL-89-04, GL-89-4, NUDOCS 9002270302 | |
| Download: ML20006F258 (6) | |
Text
6 7
~
,
- ..
.
<
~
g.;
,
u.
.
L my m -
&
.
.
j
!
p
'
O. S. NUCLEAR REGULATORY COMMISSION
REGION I
. Report No.
50-293/90-02 J
,
Docket No. 50-293
- O
'
License No. DPR-35'
l'
s Licensee':
Boston Edison' Company 800 Boyl. ton Street
Boston, Massachusetts 02199
.
. Facility Name: Pilgrim Nuclear Generating Station
,
. Inspection'At:. Plymouth,'2 Massachusetts
.
Inspection Conducted: January 8-12, 1990
.;.j Inspectors:
Meg et d
cJ Y fo ph A.4 olla, Reactor Engineer
/ date.
r Approved by:
Id 4-A/7/90
,
~
far Dr. P, K. Eapen, Chief ~
- 6 date j
.Special Test Programs Section
'
l'
Inspection Summary:
Inspection on January 8-12, 1990 (Inspection Report No.
50-293/90-02}
.
,
Areas Inspected:
Routine announced inspection of pump and valve--Inservice Test (IST) Program implementation and review of the IST~ Program with respect
,
'
to NRC Generic Letter 89-04 dealing with exemptions to ASME Code Section-XI
requirements-for IST. Also, the licensee's corrective action' program for evaluating and correcting leakage problems with local leakage barriers was
~
. reviewed. Additionally, the licensee's performance in the area of Engineering
.i and; Technical Support to the plant.was evaluated.
,l
!
Results:
No violations or deviations were identified. The licensee's
.^
implementation of insenice testing was found to be in compliance with requirements. The-licensee has addressed Generic Letter 89-04 but has several-
exemption requests outstanding which the Generic Letter does not address.
-
Corrective action for local leakage barriers was found adequate. The
' licensee's Engineering and Technical' Support of the facility was also found
'
i, adequate.
l-l ~
.
'
l-l 9002270302 900207
@
k PDR ADOCK 05000293 L
Q PDC
[J
,
'
-
l-
>
l
_ - _ _ _ _ _ _ _ _
<
.
i
.
'
h, l
.
Details P
I 1.0 Persons Contacted 1.1 Boston Edison Company
- R. Anderson, Plant Manapr J. Bellefeuille, Onsite Safety & Performance Division Manager D. Ellis, Senior Compliance Engineer
- R. Fairbank (Telecon), NED Manager (Acting)
- W. Grieves, Senior QA Engineer (QAD)
- K. Highf111, V.P. Nuclear Operations
,
- J. Kelly, Compliance Engineer
'
P. Manderino, Senior Test Engineer F. Mogolesko, Performance Engineer
- V. 0heim (Telecon), Design Section Manager (Acting)
J. Sabina, Senior Test Engineer
<
- J. Seery, Techical Section Manager
,
- R. Swanson, Regulatory Affairs Manager (Acting)
1.2 U.S. Nuclear Regulatory Commission I
- C, Carpenter, Resident Intpector
- Donotes 1%n present at the exit meeting held January 12, 19'90.'
y 2.0 In.spectino Pu,r. nose and Scope
,
This inspction wss conducted to review and assess the licensee's implementation of their pumr and valve Inservice Test Program and other
. -
activities associated with IST implementation.
It was also conducted to
R verify adheNrce to ASiM 5ection XI Code requirements and the licensee's
'
commitnonts regard'ng Generir, Letter 89-04 dealing with exemptiens to the Code.
Also, the licentte's corrective action progrn for evaluating and repairing loce.1 leakaga barriers exhibiting leakage identified by 10 CFR 50, Appendix J local leak rato testing was reviewed. Additionally, engineering and. tech 31 cal support to the plant was evaluated by reviewing the engineer-ing support for a design change, a modification, and engineering analysis of a vibration problem with the HPCI pump.
-
3.0 IST Program Implementation (73756)
-
'
The inspector reviewed the licensee's latest IST pump and valve program submi, al and associated exemption requests.
The licensee is committed to the 1980 version of the ASME Code Section XI through Winter 1980 Addenda.
The Pilgrim Nuclear Power Station is in its second 120-month
I inservice inspection interval which extends to December 7, 1992.
The
'
"IST Pump and Valve Testing Program," procedure no. 8-I-1.1, Rev. 0
,
l
/
[
.
.. -
-
i
.
.
'
,
'
i l'
has recently been updated and approved by licensee management on December 19, 1989 for use and to be submitted to the NRC for review.
l The new program submittal reflects changes to support commitments made
,
in their response to NRC Generic Letter 89-04. Also in support of their
'
response to the Generic Letter and changes to the IST_ Program, the license
'
is in the process of revising IST implementing procedures. To date, the licensee has reviewed each safety related system to ensure that the ap-
'
propriate pumps and valves are included in the program.
The licensee has l
recently revised its administrative document " Administration of Inservice
,
Pump and Valve Testing," procedure no. 8.I.1, Rev. 5, November 13, 1989
'
,
which controls program implementation, to support the new program. They will prepare a new station instruction to provide the method for determin-ing realistic valve stroke time criteria and will revise the stroke time
'
,
acceptance, alert and action criteria for each power operated valve in the program. The following priorities and milestones have been established by the licensee, and accepted by the NRC for the remaining IST effort.
-
Schedule:
Submit IST program and the statement of 12/15/89(completed)
conformance
,
Compkte quarterly pump and valve procedures" 06/30/90
!
(23 proceJures)
'
Complete cold shutdvan pump or.d valve procedures 06/30/9'O
(1) procedures)
Comrlete valve leakage procecures 11/30/90
,
(6 procedurn)
Complete refueling outage procedures M /30/9C
(Sprocedures)
l IST prog'em full implemer.tation Ett 9,efueling
Outage (Early 91)
Completion of plant modifications Long Term Plan
In addition to the above, the licensee has 11 new relief requests which I
require review by the NRC. Most of these were created because of the increased scope of coriiponents being tested under the updated IST Program. These 11 relief requests address issues not specified within the scope of Generic Letter 89-04. Another 5 new relief requests were submitted by the licensee wnich address specific issues identified in the
,
p Generic Letter.
Those existing relief requests which have been revised were resubmitted to the NRC.
l l
.
.-
.-
,
-
,
-
-
i
i
The inspector determined that upon completion of the above schedule by
'
the licensee and final review by the NRC of requested exemptions, the
'
licensee's IST program will be fully implemented.
4.0 Corrective Action Program For Valves
,
The inspector reviewed information documenting the licensee's efforts in
!
evaluating and implementing corrective action for valves in the 10 CFR 50, Appendix J Local Leak Rate Test program with demonstrated leakage problems.
It n s found that the licensee does trend and evaluate these valves for repair or replacement and that there is evidence that the
corrective action program for this has been effective.
The licensee's
'
corrective action program was formally initiated and caused the repair or replacement of valves at Pilgrim during the last three outages. As a result 17 valves have been replaced as part of the " Valve Betterment Program",in the following systems: Containment Atmospheric Control,
'
High Pressure Coolant Injection, Main Steam, Reactor Water Cleanup, Instrumentation Air, Residual Heat Removal, Reactor Sample, and l
Containment Sump Systems.
In addition, 8 MSIV's and 4 feedwater check
'
valves have been modified to improve leak tightness and integrity.
Co*rective actions initiated as a result of the Valve Betterment reogram
.
also includss improvements in affected vendpr manuals and other vendor i
documents. Durinq Refuelirg Outage 7, a Local Leak Rate Te.it (LtRT)
Failure Analysis Ttam com:;osed of engineers from both Euc1 car Enginaring and Pla'it Departuents was formed to investig ne ea:h U RT failure, deter-
>
utne root cause, and recommend corrective action.
The licenan is curreatly
'
l implementing an LLRY Trending Program on a computerized database.
This
prograt is intended to enhance the licensee's abilities for data correla-tioa wch as valve leakaga histories and manufacturers.
It is also intended
to make penetration cenfiguration and component data more retdily available
'
to the LLRT Cngineer.
Based on the above review, the inspector concluded that the licensee has an effective corrective action program in place for trending, evaluating, and making repairs or replacing problem valves. No unacceptable
,
conditions were identified.
5.0 Design Changes and Modifications (37700)
The objective of this inspection was to ascertain that design changes
and modifications to the plant are receiving adequate engineering and
'
technical support and to verify conformance with the requirements of the Technical Specifications (TS),10 CFR, the Safety Analysis Report, and the licensee's Quality Assurance Program.
This objective was accomplished by performing a detailed review of a selected modification, and two Engineering Service Request's (ESR's) for engineering assistance to the plant.
l
I
.
.
.
.
.
.
.
.
.
.
..
.
.
-
-
.
L
.
~
5
.
5.1 Engineering Support to Resolve Issues Identified in Licensee Event Reports (37828)
The inspector reviewed the Engineering and Technical Support which resulted in corrective action for two events reported in accordance with 10 CFR 50.73, " Licensee Event Report System," and Engineering
.
and Technical Support for the HPCI Main Pump which was displaying higher than normal vibration readings as identified by inservice testing.
Engineering and Technical Support for the following LER's was reviewed:
LER 88-017-01, " Crack in the Yoke Portion of a
,
Residual Heat Removal System Valve," and LER 89-013-00, "High Pressure Coolant Injection System Inoperable due to Inoperable Motor
<
Operated Valve."
LER 88-017-01 involved a crack which was discovered in the yoke portion of RHR system Loop B valve MD-1001-28B.
Corrective action
,
for this situation resulted in removal of the valve yoke and metallurigical examination, disassembly and inspection of valve internals, stem, and rnotor operatoe, repair and partial replacement of the valve yoke, review of the cperating history of the valve and similar Loop A valve, examination of the simi1Sr Loop valve uke, and test of the motor operator spring pack and HMATS test upon valve retssembly.
This LER resulted in extensive failure analysis by the liensee who J
employed the assistence of an expect in the metallurgical fiqld.
I At a result of the failure analysis, a design r.hange to the v3 /es
yoke, and similar 1.oop A valve yokt war, instituted. The inspector reviewed Plant Oerign Chance (POC) pachse nc. 88-23 which contiolled the modtficatien to the yde ord discussed the ent,ineerir.;l and technir,al support which went into tt with cognizant licensee personnel. This engineering effert was thorough and of good quality.
LER 89-013-00 involved the inoperability of the HPCI systen due to an inoperable HPCI systerr. motor operated valve (MO-2301-3)
discovered during a HPCI system operability test. The valve, normally closed, is located in the steam supply piping to the HPCI system turbine.
On March 24, 1989 at 1814 hours0.021 days <br />0.504 hours <br />0.003 weeks <br />6.90227e-4 months <br /> a scheduled (quarterly) HPCI system pump operability test began and was
.
conducted from the control room.
Upon moving the control switch
!
for valve no. MO-2301-3 to the open position for a start of the HPCI system turbine, a panel alarm for MCC-09 Loss of Control 125 or 250VDC occurred and the valve would not open. Because the valve
)
would not open, the HPCI system was declared inoperable.
The cause for the failure of the valve to open was two loose screws used to adjust the valve's torque switch setting. The loose screws affected the torque setting and consequently caused damage to some of the valve operator internals and failure of the valve operator motor
!
_ _ _ _ _ - _ - _
,
-
o
.
'
-
i i
windings. Corrective actions taken by the licensee are as follows:
'
The valve operator was repaired and the motor was replaced, i
The torque switch was set and the screws were torqued to 18 j
toch -unds.
MOVATS valve testing was performed with ecceptable re n Additional corrective actions planned include inspection
'
of einer ty-related motor operated valves, installing torque switch lir.o a r plates, and revision of applicable valve maintenance procedures.
5.2 Engineering Service Requests
The inspector reviewed BECO Engineering response to Engineering I
Service Request (ESR No.89-243) submitted to the Nuclear Engineering Department (NED) requesting guidance in evaluating the MO-2301-3 valves condition and scope of work required.
The inspector found the engineering support which recommended the corrective actions taken above also to be thorough and of good
>
quality.
'
Addf tionally, engineering support for a HPCI pump bearing vibration problem was evalua'.eo by the inspector.
In this case, an Engineering Stervice Rsquest was wi, Men because HPCI pump r
bearing velocity and displacerer,t vibratior readings obteined during
IST quarterly HPCI tuting indicatted thr pump was ruaning rcugh.
Displacewnt rcadings were in the test acceptance range but were
+
higher thar, normal. The Nuclear Engineering Apa rtment. concluded g
thet +he purps performance was acceptable.
However NED recommerded
'
that t% IST test engineer should continue to trend test data. This
,
cottclusio'1 vas arrived at in a logical manner utilizing historic tust data whic.h indicated similar characteristics in the past, and consider-ing the 'nechanical arrangement Turbine / Pump /Reductioa Gear / Booster Pump, of the components.
The response to the Engineerlag Service l-Request showed that there was good cooperation and communication l
among Nuclear Engineerina Systems Engineering and IST Test Engineer-L ing in evaluating the acceptability of the pumps performance and in l
determining continued operability with the contingency for IST L
Engineering to trend the pumps performance.
The inspector found the engineering support in this case also to be of good quality.
No unacceptable conditions were identified.
6.0 Exit Meeting
'
h Licensee management was informed of the purpose and scope of the
'
inspection at the entrance interview, The findings of the inspection were periodically discussed and were summarized at the exit meeting on January 12, 1989. Attendees at the exit meeting are listed in Section 1.0 of this report. At no time during the inspection was written material provided to the licensee by the inspector.
The licensee did not indicate that the inspection involved any proprietary information.
.I