IR 05000219/1971004
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U. S. ATOMIC ENERGY. COMMISSION DIVISION OF COMPLIANCE i
REGION I
h CO Inspection-ReportINo.
50-219/71-04 Subject:
Jersey' Central' Power & Light Company
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. Oyster Creek.1 License No.
DPR-21 Location:
Forked River,'New ' Jersey Priority i
Category
'C~
Type of Licensee: GE 1690 MWt BWR
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. Type of Inspection:
Special, Announced
' Dates of Inspection:
November 5. 1971 October 7 & 8, 1971 Dates of Previous Inspection:
N Principal Inspector:
LL,(.
fM.
Y,
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'T. Young, Jr.,
ictor pe'c r
/Dat/
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Accompanying Inspectors:
None Date Date Other Accompanying Personnel:
None Date
/3/7/
Reviewed By:'
w w-r-r
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ba te'
R. L.-Spes d, Reactor Inspector
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Proprietary'Information:
None
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9604190'101'96'0213 Y
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PDR FOIA-i DEKOK95-258-PDR
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Section I Enforcement Action: None Licensee Action on Previously Identified Enforcement Matters: Not inspected Unresolved Items:
A.
Quality assurance documentation for relief valve No. NR108E and results of flow capacity test.
(Paragraph 3)
B.
Quality assurance documentation for new valves installed in the core spray system (CSS), isolation condenser piping (ICP) and poison system (PS). (Paragraphs 4 and 5)
Status of Previously Reported Unresolved Items:
A.
Drywell Compressed Nitrogen System (NCS)
JCP&L has installed two filters in the NCS piping downstream of the compressors to remove possible contaminants which could enter the instrument air system loads within the drywell. This item is considered closed.
B.
Containment Isolation Valves for the Drywell and Torus Oxygen Sampling Lines edMQi JCP&L has installed double isolation valves in both the drywell and torus oxygen sampling lines. This item is considered closed.
C.
Stack Monitor JCP&L was installing a new isokinetic probe at the 156 ft. elevation of the stack along with a new I-beam support structure (Inquiry Report No. 50-219/71-04). The completed installation and testing results for this probe will be reviewed during a future C0 inspection.
Unusual occurrences: None
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- 2-Persons Contacted:
T. McCluskey, Station Superintendent
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'D.
Ross, Technical Supervisor'
J.- Sullivan, Assistant Technical Supervisor E
E. Riggle, Maintenance Supervisor
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N. Goodenough, GPU, QA Engineer Management. Interview:
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The following subjects were discussed.with Mr. Ross on November 5, 1971:
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A.
The inspector stated that'he had' observed that the fifth relief valve was installed and its discharge was piped below the water level in the torus. The inspector stated that a review of site documentation showed that the setpoint of: this valve had been
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set at 1125 psig (same as the' other four valves), and 'that this
information would be reported to DRL.
(Paragraph 3)
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13.
The-inspector. stated that QA documentation for the fif th relief valve and the new valves installed in the CSS, ICP and PS would be reviewed'during the next CO inspection. Mr. Ross stated that-QA documentation for these valves would be available.
(Paragraphs 3, 4 and 5)
C.
Mr. Ross stated that before the next outage, a tool' would be 9,gg designed and fabricated to re-install the speciman holder.
.(Paragraph'6)
D.
Mr. Ross was informed that no items of noncompliance were observed.
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Sectior II Additional Subjects Inspected, Not Idettified in Section I, Where No Deficiencies or Unresolved Items were Found
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1.
General
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A special inspection was conducted to insure that the fifth relief valve had been installed, that its discharge had been piped below the water level in the torus and that its relief setpoint had been set at the same value as the other four relief valves.
Installation of this valve was required as part of the licensee's application to increase steady state power level up to 1930 MWt.
2.. Facility Procedures
a.
Test procedure for relief valve No. NR108E.
b.
Functional test procedure for reliev valve No. NR108E.
c.
Setpoint adjustment procedure.
Details of Subjects Discussed in Section I 3.
Relief Valve No. NR108E Installation
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The inspector observed that the fifth relief valve was installed and that the five relief valves were identical per name plate
,pAA data. The discharge of the fifth valve is piped to one of the two existing down comers which connects to the vent header in the air space of the torus. Therefore, any flow from this valve will discharge below the water level of the torus.
Site records disclosed that the relief setpoint for this valve was set at 1125 psig (same setpoint as the other four relief valves).
QA documentation for the valve installation had not been assembled and will be reviewed during the next 60 inspection.
(See Item B of Management Interview.)
The flow capacity of this valve will be checked after plant startup and the results will be reviewed at the time of the next inspection.
4.
CSS Check and ICP Block Valves
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The inspector observed that the subject valves were welded into their respective systems, but that the valve certifications, the welder's qualifications and nondestructive testing results were unavailable.
(See Item B of Management Interview.)
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PS Valves Mr. Ross informed the inspector that two vcives hau oeen installed
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in the poison system, but that the QA documentation for these
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f valves had not been assembled. The inspector stated that installation of these valves and their QA records would be reviewed during the next inspection.
(See Item B of Management Interview.)
6.
Removal of Flux Wire lloider Mr. Ross luformed the inspector that the flux wire holder was scheduled to be removed on this outage, but it was discovered that the flux wire holder was welded to the specimen holder which is latched to the inner wall of the pressure vessel (PV).
(The specimen holder containing tensile and inpact samples was to remain in the PV for four years.) After both holders had been removed and cut apart, it was discovered that the specimen holder could not be re-installed with the tools existing at the site. There are still two specimen holders remaining in the PV.
(See Item C of Management Interview.)
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UNITED STATES f
' ATOMIC ENERGY COMMISSION
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g OlVISION OF COMPLIANCE 201 645
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l REGION t 570 BROAD STREET NEWARK. NEW JERSEY 0710?.
s DEC 13 E7i
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G. L..Madsen, Acting Senior Reactor Inspector Division of Compliance, Region I CO INSPECTION REPORT NO. 50-219/71-04 JERSEY CENTRAL POWER & LIGHT COMPANY
' OYSTER CREEK 1-BWR I am satisfied that the fifth relief valve has been installed, that the discharge has been piped below the water level in the e-torus and that the setpoint was set (and tested) so that it is identical to the other four relief valves.
The valve certifications (QA folder) will be reviewed-by Floyd
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on his.next inspection.
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IL uclS Y
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T. Young Reactor Insp,ctor j
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U. S. ATOMIC 1:NERGY COMc!ISS10:4 DIVISION OF COMPLIANCE RCOICI' I Field Notes for:
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Type of Lic'r<;ce: ~$ S,Q b b b 01M, OW k_
I Type of Inspection:
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Dates of Inspection:
4'2(hM @b d,/W Dates of Previous Inspection:_f{
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Principal Inspcetor:
[v0N /O, T
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i 3944 NOV 2 01971 R. T. Carlson, Acting Chief, Reactor Testing & Operations Br.
Division of Compliance, IM L
CO I!MUIRY REPORT No. 50-219/71-12 n
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JERSEY CENTRAL POWER & LICllT COMPA!W g' ~
l OYSTER CREEK 1 - BWR i
CatPLETE !#SS OF INSTRIMDIT AIR The subject inquiry report is forwarded for your action.
This failure demonstrates how a single failure can cause a complete loss of instrument air at this facility. This event warrants a review j
by DRL relative to the need for the installation of check valves in the air compressor.; discharge lines. Additionally, consideration should be given to requiring automatic scram protection for loss of instrument air pressure, to prevent recurrence of randem rod scramming at boiling water reactors.
ifhd-The licensea stated enat he would make a written report of the failure to DRL, however, he had not decided whether the report would be a 10 day report or an information report.
C. L. Hadsen Acting Sr. Reactor Inspector Enclosure:
Subject Inquiry Report cc:
E. G. Case, DRS (3)
R. S. Boyd, DRL (2)
R. C. DeYoung DRL (2)
D. J. Skovholt. DRL (3)
H. R. Denton, DRS (2)
A. Giambusso, CO L. Kornblith, CO O
R. H. Engelken, CO Regional Directors, CO g
DR Central Files omer >
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CO Inquiry Report No. 50-219/71 12 Subject: Jersey Central Power & Light Company License No.: DPR-16 Facility: Oyster Creek 1
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Title: Complete Loss of Instrument Air
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Prepared by:
I F. S. Cantrell, Reactor Inspector Date l
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A.
Date & Manner AEC was Informed:
By telephone call from Mr. T. McCluskey, Station Superintendent.
November 17, 1971. Further details were obtained during a special
site inspection on November 19, 1971.
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B.
Description of Particular Event of Circumstance:
While operating at 1400 MWt on November 16,1971, the 6" flexible connection in the line between the discharge of one of the inattu -
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ment air cocipressors and the air receiver, ruptured catastrophically.
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,4j This line is not equipped with a check yalve sad the standby com-1, pressor was not capable of maintaining air pressure. The control room operator received an alarm " air receiver low pressure" and s
" control rod drive low air pressure". The operator observed that
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some control rods were serenfng individually and that air pressure was dropping. He initiated a manual scram.
(The emergency procedure specifies 50 psi as the pressure at which the operator should initiate a manual scram.) The failed section of pipe was isolated and the standby air ccx:rpressor recharged the system to > 50 psi in approxi-mately 20 minutes.
C.
Action by Licensee:
A replacement flexible connection was obtained and installed prior to the return to power. The connection was fabricated with a double reinforcement braid instead of the original single braid in order
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to minimize the possibility of future blowouts. The licensco is considering installing check valves in the compressor discharge lines.
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3944
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NOV 2 6.1971
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R. T. Carlson, Acting Chief, Reactor Testing & Operations Br.
Division of complianae, BQ
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CD INQUIEf REPORT NO. 50-219/71-11 JERSEY CatTRAL PolfER & LIGRT CCHPANY Of8TER MEEK 1. EliR
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FAnar OF MAIN STEAN IS01ATION VALVE TO CLOSE The subject inquiry report is forwarded for your action. This failure ag be generic in nature in that two of four valves examined had the sand defect.
The subject valves are 24" Atwood Morrill valves with a Hydro-Line Manufacturing Company valve operator, ibdel 612 003-1B, complete with hydraulic dash pot (Model N2R, 6" bore x 13" stroke).
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It is raa w d that all 11eensee's be requir.vl to evaluate their M81Vs in light of the above experience to determine if the valves in their facilities are subject to the same failure. Other BWR licensees
in Region I have been notified of this failure. We will keep you informed of further developments.
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i 0. L. Madsen
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Acting Sr. Reactor Inspector Reclosures
Subject Inquiry Report
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cc E. G. Case, DR8 (3)
R. 8. Boyd, DRL (2)
R. C. DeYoung, DRL (2)
D. J. Skovholt. DRL (3)
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H. R. Denton,.DRS (2)
A. Cimabusso, 00 k[
L. Kornblith, 00 R. H. Engelken, CO i
Regional Directors, 00
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11/26/71 we,
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C0 Inquiry Report No. 50-219/71-11
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Subject: Ja;r -*-al Poisar & u.htr'- --
h License me.: nrn-16 Facility: Oyster Creek 1 Title:
Failure of Hain Steen Isolation Valve OtSIV) to close Prepared by:
F. S. Centre 11, Reactor Inspector Date
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A.
Date & Manner ABC was Infommed:
By telephone ea11 fran Mr. T. McCluskey, Station Superintendant, November 17, 1971. Further details were obtained in a field inspection on November 19, 1971.
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B.
Description of Particular Event or Circunstance, s
While measuring the closing time prior to a reactor startup, one HSIF failed to close. The failure to close was caused by inter-p
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forense.between e eegment of the " cushion sped"tand.the-of o - e
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the hydraulic dash pot.
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Action by Licensee:
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AninspectionoftheotherHSIVsshowedthatoneother" cushion
spud" was cracked, however, valve operation had not been impelred.
The defective "cushipu spudk" were replaced with pieces fabri' ated t
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totheoriginalspecificationsandalloftheHSIVs(4)werere-\\
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tested satisfactority. The licenses stated that he would make g"
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a written report of the HSIV failure with his evaluation of the cause of the failure, within ten days as required by his license.
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l The licenses stated that the manufacturer reported that this was I
the first reported failure of the cushion apud.
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3944
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M, NOV 261SM
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R. T. Carlson. Acting Quief, Reactor Testing & Operations Br.
Division of Compliance, BQ CO INQUIRY REPORT No. 50-219/71-10 JERSEY CENTRAL PONER & LIGNT CGtFANY OfSTER R EEK 1 - BNR 180EATION COMENSEE CONDENSATE VALVE FAIIDER The std> ject inquiry report is forwarded for your information.
A subsequent. site inspection disclosed an iten of noncompliance in that the reactor was made critical and remeter pressure was increased to 800 poi for control rod testing with one isolation condenser inoperable.
Power operation is permitted for seven days with one isolation condenser inoperable; however, both are required for startup. It appeared fran discussions with Mr. Carroll, Operations Supervisor, that the reactor was at appresimately 10 left and appresinately 800 psi when he realized
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M that both isolation condensers wore required for'startup. A decision was made to complete the control rod testing before going ta cold shutdown. This was identified to the licensee as an item of noncompliance with their Technical specifications.
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G. L. Madsen
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Acting Sr. Reactor Inspector i
Enclosures
Subject Inquiry Report
1.
cc E. G. Case, DRS (3)
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R. S. Boyd, DRL (2)
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R. C. DeYoung, DRL (2)
D. J. Skovholt, DEL (3)
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H. R. Denton, DRS (2)
A. Giambuseo, 00 L. Rorablith, 00 R. H. Engelken, 00
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Regional Directors, CO V
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11/23/71
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tbrtu A EC-318 (Itet. 9-63)
U.S.GOVERhMENTMMUNG CmCE 1986-@364-596
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CO Inquiry Report No. 50-219/71-10 Suoject: Jersey C-*ral Power & H =h* C - any
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License No. _ Drm-16
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Facility: Oyster Creek 1 Title:
Isolation Condenser C + = ate Valve Failure Prepared by:
F. S. Cantrell, Reactor Inspector Date A.
Date & Manner AEC was Infor d By telephone call from Mr. T. HoCluskey, Station Superintendent,
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November 19, 1971. Further details were obtained in a field in-spection the same day.
B.
Description of Particular Event or Cirmanstance:
The isolation condensers are set up with only the DC motor operated valve closed in order to permit activation without depending on AC power. While testing the systens with the reactor shutdown on November 17, 1971, the DC operated valve on the B condenser would g
..not,open., Investigation.showed,that.the mo$or,was shorted out.'.,-
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Action by Licensee:
The motor was returned to the vendor to be rewound, was re-installed
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and tested satisfactorily before the reactor was returned to power.
l The licensee plans to make a written report of this failure to the j
Conmission within 10 days.
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