IR 05000270/1974003
| ML19317D384 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 05/13/1974 |
| From: | Jape F, Robert Lewis NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19317D378 | List: |
| References | |
| 50-270-74-03, 50-270-74-3, NUDOCS 7911270592 | |
| Download: ML19317D384 (14) | |
Text
,r.hdds Ut4lTED STATES
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Tgf a e t. r a r,i. e.n,,. Jo3c 3 RO Inspection Report No. 50-270/75.-3 Licensee: Duke Power Company Pcwer Building 422 South Church Street Charlotte, North Carolina 28242 Facility:
Oconee Unit 2
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Docket No.:
50-270 License No. : DPR-47 Category:
B2 Location:
Seneca, South Carolina Type of License: B&W, PWR, 2568 Mw(t)
Type of Inspection:
Soutine, Unannounced Dates of Inspection: April 9-12, 1974 Dates of Previous Inspection: January 22-26, 1974 Principal Inspector:
F. Jape Reactor Inspector Facilities Test and Startup Branch Accompanying Inspector: None I~
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Principa1 Inspector:
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F. Jape, Reactor Inspedor Date Facilities Test and Startup Branch CeD
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Reviewed By:
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R. C. Lewis, Acting Chief Date
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Facilities Test and Startup Branch
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'R0 Rpt. No. 50-270/74-3-2-
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Smry of Findings 1.
Enforcement Action A.
Violations None B.
Safety Items
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None II.
Licensee Action on Previously Identified Enforcement Matters A.
Violations DPC's response on violations described in R0 Report No. 50-270/74-1, dated May 21, 1974, has been received and is currently being evaluated.
B.
Safety Items None III.
New Unresolved "tems
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74-3/1 Temporary Station Modifications The licensee does not have a procedure for processing temporary station modifications.
(Details, paragraph 2)
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74-3/2 HP-31 Reset Interlock A change to modify the operation of HP-31 is classed as
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non-safety related.
Licensee is reviewing this item to determine if it should be classed as safety related.
(Details, paragraph 5.c)
74-3/3 H1;h Energy-Line Bredk >bdifications Work on this modification has not been completed.
Licensee management has committed to completing the modifications prior to startup from the current outage for pump repairs.
(Details, paragraph 8)
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IV.
Status of Previously Reported Unresolved Items s
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74-1/1 Station Reveiv Co==ittee Not inspected.
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i 73-1/2 Co=munication of Activities Affecting Reactor Operations Not inspected.
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74-1/3 Records of Radioanalysis Results Not inspected.
73-8/2 Valve Wall Thickness of Valve 2-RV-67
1 A meeting with DPC on March 1,1974, was held to discuss the l
power operated relief valve. As a result of the meeting,
supplemental responses, dated March 23 and 24,1974, have been received and is currently being evaluated by Region II.
This item remains open.
r 73-8/1 Body Wall Thickness of Valves 2-51-244 and 2-51-245 i
Corrective measures have been completed by DPC.
A Region 11 inspector will review these measures on a
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subsequent inspection.
i V.
Unusual Occurrences None n
VI.
Other Significant Findings
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NSSS Site Personnel Changes The following changes in the B&W Nuclear Services Department were announced April 5,1974:
a.
Mr. R. J. McConnell (Site Operations Manager) has been appointed Manager of the Tiant Startup Service Section, and will return to the B&W Lynchburg of fice.
b.
Mr. B. L. Day (Site Operations Engineer) has been appointed
Site Operations Manager.
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Mr. R. J.. Baker, Jr.,' has been named to fill the position of c.
Site Operations Engineer.
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VII.
Management Interview A canagement interview was held on April 12, 1974, wich the following in attendance :
Duke Power Company J. W. Ha:pton - Assistant Plant Superintendent R. M. Koehler - Staf f Enginear
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J. M. Davis - Maintenance Engineer O. S. Bradham - Technical Support Engineer L. E. Schmid - Operating Engineer
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Subjects discussed included:
A.
Fuel Unloading and Reloading Several comments on the fuel unloading and reloading procedures were discussed.
All were resolved except one which has to do with temporary station modifications.
The licensee indicated that an administrative instruction would be prepared on this item.
The inspector stated that this item would be carried as an unresolved item.
(Details,
paragraph 2)
B.
Loose Parts Retrieval and Reactor Vessel Internals Examinat ion Procedures for recovery of loose parts and examination of reactor vessel internals were reviewed.
The inspector had no comments on the procedures.
(Details, paragraph 3)
C.
Reactor Coolant Pump Repairs
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Procedures used for disassembly and reasserbly of RC pumps were reviewed and the inspector had no comment.
(Details,
paragraph 4)
D.
RC Pump Seal Water System Modifications Eight modificaticns, which are currently being installed on the RC pump seal water system, were reviewed.
Several operating procedures, alarm procedures, emergency procedures, and instrument procedures will require revision to incorporate
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the effects of these modifications. >bnagement stated that the appropriate procedures would be revised, approved, and issued prior to startup.
(Details, paragraph 5)
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E.
ROIR 74-1 and 74-2 The licensee's responses to Information Requests 74-1 and 74-2 i.
were verified by the inspector.
(Details, paragraphs 6 and 7)
i F.
High Energy-Line Break Modifications
The schedule for completing the modifications, as described in
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i MDS Report No. 0S-73.2, dated April 25, 1973, and Supplement 1, i
dated June 22, 1973, was discussed.
This item will be added to i
the unresolved items list pending cocpletion of the work and
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followup by Region II.
(Details, paragraph 8)
j G.
Previously Reported Unresolved Items i
The status of previously reported unresolved items was discussed.
(Summary,Section IV)
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H.
Enforcement Action
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The status of previously identified enforcement items was discussed.
(Su= mary,Section II)
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bI DETAILS Prepared By:
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F. Jape, Reactor I'nspector Date Facilities Test and Startup Branch i
Dates of Inspection: A ril 9-12, 1974
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I Reviewed By: I [, ueh
(I R. C. Lewis, Acting Chief
' Date Facilities Test and Startup Branch
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1.
Individuals Contacted Duke Power Company (DPC)
H. R. Lowery - Shif t Supervisor B. Earnhardt - Control Operator E. E. Hite - Junior Engineer
D. Rogers - Junior Engineer
R. M. Koehler - Staff Engineer
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J. Bracket - Junior Engineer J. Davis - Maintenance Engineer 2.
Fuel Unloading and Reloading All fuel was removed from the reactor to retrieve loose objects in the bottem vessel head.
Fuel unloading began February 25 and was conpleted February 28, 1974. All asse=blies were removed without difficulty except for 2A07.
This one fuel assembly required approximately 800 lbs. of extra force to jar it free.
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Fuel reloading was initiated on March 25 and comp 1,ted on
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April 2, 1974.
Thirteen fuel asse:blies were inspected using a periscope and a TV camera. No damage was observed.
Fuel assembly 2A07 was examined
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by Duke Pcwer and B&W personnel.
This assembly was declared to be acceptable for reloading.
No difficulty was experienced when this
- aembly was reloaded.
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The inspector had the following comments on OP 150 215, " Fuel Unloading and Reloading":
a.
Minimum Count Rate During Reloading Change No. 16 authorized having only one detector in service when no reactivity changes were being made.
In making the change the mini =um count rate for an operable detector was deleted.
Licensee management stated that it was not intended that the minimum count rate be deleted.
The minimum count rate of 2 cps was re-instated.
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b.
Incore Detector Response
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A note on page 12 of the log indicated that "A" and "B" detectors I
had less than 2 cps.
The inspector asked if this was a valid statement. Licensee management acknowledged that the statement was incorrect and should have stated that "A" and "B" detectors had mor'e than 2 cps. A corrected log entry was made.
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c.
Modification to Transfer Mechanism Change No. 3 to OP 1506/1, " Fuel and Component Handling,"
authorized use of a tecporary modification to the trancfer mechanism.
The modification involved installing a push button bypass around a magnetic limit switch. The magnetic limit switch was being actuated by a wheel on the transfer
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carriage instead of the actuation plate.
The result was to stop carricge movement about 6 inches short of the upender.
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The inspector questioned the method used to authorize installation of this change. Licensee management co=mitted
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to providing an administrative procedure to cover temporary
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stati;n modification.
This item will be carried as an unresolved item until the new instruction is issued.
3.
Loose Parts Recoverv The inspector reviewed the following three operating procedures and had no comments:
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a.
OP 200/40, " Controlling Procedure for Loose Parts Retrieval" b.
OP 200/41, " Examination of Reactor Vessel Internals" OP 200/43, "Leose Part(s) Recovery" c.
Material removed from the reactor vessel bottom head consisted of the following:
A screw approximately 1-1/2 inches by 1/2 inch diameter, a.
b.
A small set screw.
c.
The missing cap screw frca RC Pump 2B2.
d.
About a cup full of metal shavings and grit.
Missing material not yet accounted for:
A 1/4 inch by 3/8 inch bolt off the periscope bracket.
a.
b.
Roll pin from RC Pump 2B2.
The licensee stated that these objects may be in the lower portion of the refueling canal.
This area is to be drained before startup and searched for the missing items.
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Examination of the internals revealed no damage from the loose parts. The fue.' support bracket for fa 1 assembly 2A07 was
t examined and a very small burr was.ie ' ::ed.
This was filed and no difficulty was experienced when the fuel asse=bly was replaced
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in this position.
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Reactor Coolant Pu=p Repairs Maintenance procedures used for acco=plishing repairs of the RC pumps were reviewed by the inspector.
There were no comments or questions concerning these procedures.
Mainten.:nce procedure MP 1400/35A, " Installation and Removal of RC Punp," MP 1400 353, " Assembly and Disse bly of RC Pump,"
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j and MP 1400/34, "RCP Tandem Seal Removal and Replacement," were
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followed during repair of the reactor coolant pumps. A chronological i
log was maintained during pu=p repairs.
A clean area was setup prior to disasse=bly work.
The area was posted with radiation warning notices and radiation work permits were issued to establish I
work conditions and hecith physics monitoring requirements for the job.
Station modification 0-145-S was installed on all 'four RC pumps.
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This modification provided an additional pin to lock the cap screw in the pump impeller hub and to permit both lock pins to be welded
in place.
Detailed instructions were provided to install the change.
The change was approved by the Station Review Co=mittee, 3~
Plant Superintendent, Assistant Vice President, Steam Production j
and Engineering, on February 15, 1974.
The inspector had no co= cents concerning the RC pump repairs or the
modification.
5.
RC Pump Seal Water System Modifications Eight modifications are currently being installed to the RC pump seal water system to prevent recurrence of the seal failure l
incident.
The eight items are described below:
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a.
Seal Return Valve Time Delay The individual RC pump seal return valves previously closed af ter a 50-second time delay when both seal injection and
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component cooling were lost or seal injection was lost and
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the pu=p was off.
The codification will change the time delay to 5 seconds.
The basis for this change is to minimize the flow of hot reactor coolant water into the seals after loss of normal seal water.
This change is covered by Station Modification Report (SMR)
0-114-5, and was reviewed by the Station Review Committee (SRC)
on March 14, 1974, and approved by the Plant Superintendent
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R0 Rpt. No. 50-270/74-3-5-Assistant Vice President, Steam Production, and Engineering on March 14, 1974.
b.
Seal Bleed-off Interlock An interlock to close the seal return isolation valve, if all of the individual seal return valves are closed, is being added. This interlock action will give further assurance that the seal bleed-off flow is stopped when all of the individual seal return valves are closed.
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This change is covered by SMR-0-125-S, and the SRC reviewed it on March 26, 1974, the Plant Superintendent approved the change on March 29, 1974, and the Assistant Vice President Steam Production, and Engineering on March 5, 1974.
c.
HP-31 Reset Interlock Previously, seal ' injection inlet flow was controlled by a flow controller and control valve HF-31.
If seal injection was lost, HP-31 would open wide and if seal injection was re-established, flow could be excessive, resulting in thermal shock to the seals. To prevent this, an interlock is being added to close HP-31 on loss of seal injection. The interlock requires the operator to switch HP-31 to manual and re-establish flow at the proper rate before returning to auto control.
This change is covered by SMR-0-128-S.
The SRC did not review this change since management classed it as nonsafety related.
The Plant Superintendent approved the change on March 29, 1974, Assistant'Vice President on March 26, 1974, and Engineering
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on March 22, 1974.
d.
Te=perature Monitoring Two thermocouples are being added to =onitor te=peratures at:
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Upper seal adjustment gage opening at the top of the pump, i
near the seal. leakage chamber drain, and l
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between the bearing cavity and the lower seal.
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The temperature data will be indicated and recorded in the control room, l.
This change is covered by SMR-0-129-S.
The SRC did not review this change since management classed it as nonsafety related.
The Plant Superintendent approved the change on March 29, 1974,
Assistant Vice President, Steam Production, on March 26, 1974, and Engineering on March 22, 1974.
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e.
Total Seal Injection Recorder A chart recorder is being provided to record total seal injection flow.
The recorder will be located in the control room and will provide,information for the operator's use.
The change is covered by SMR-0-126-S, and was classed as non-safety related.
SRC did not review this change.
The Plant Superintendent approved the change on March 29, 1974, Assistant Vice President, Steam Production on March 26, 1974, and Engineering on March 22, 1974.
f.
Seal Leakage Flow Measurement
A means is being provided to measure seal leakage flow for each RC pump and record these data in the control room.
Alarms will be provided to annunciate if flow exceeds a predetermined value.
This change is covered by SMR-0-130-S and was reviewed by SRC on April 1, 1974.
The Plant Superintendent approved the change on April 1, 1974, Assistant Vice President, Steam Production, on March 18, 1974, and Engineering on March 18, 1974.
j g.
Component Cooling Flow A means is being provided to measure and record component cooling water flow to each RC pump.
Alarms will also be provided to annunciate on low flow.
This change is covered by SMR-0-127-S and was classed as non-safety related. The Plant Superintendent and-the Assistant Vice President, Steam Production approved the change on March 29, 1974.
Engineering approved the change on March 22, 1974.
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Component Cooling Flow Orifices Orifices are being installed in the inlets to each RC pump cooler.
Previously flow was controlled by throttling valves. With an orifice installed, the throttle valves will be full or nearly full open.
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This change is ccvered by SMR-0-175-S and was. classed as non-safety related.
The Plant Superintendent approved this change on March 28, 1974, Assistant Vice President, Steam Production, on March 26, 1974, and Engineering on March 21, 1974.
These changes were being processed as prescribed in Administrative i
Procedure 10. " Station Modification," dated October 15, 1973.
The inspector had no questions or comments on these changes except for Item C "HP-31 Reset Interlock." This change is
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classed as nonsafety related. The inepector asked how this determination was made.
Licensen management stated that the Plant Superintendent makes this determination when he reviews a station modification request.
The inspector stated that since this change is intended to ensure or protect the integrity of the reactor coolant boundary, it would appear to be safety-related.
This item will be carried as an unresolved item.
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The inspector also noted that Items e, d, e, f, and g provide information concerning seal water status.
The inspector asked how this information was to be used.
Licensee management stated that appropriate operating procedures, alarm procedures and emergency procedures would be revised to incorporate this data.
All revisions are to be completed prior to reactor startup from the shutdcwn for pump repairs and internals
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inspection.
There were no further questions or co==ents en this ites.
6.
ROIR 71-1. " Abnormal Occurrences in Pipine Svstems" Actions requested by Regulatory Operations Information Request 74-1 were discussed and confirm?! with licensee management.
DPC's response dated Fabruary 6,1974, was verified by the inspector.
A review of all incidents related to Unit 2 revealed that no unanticipated movement or damage to piping systems have occurred.
A visual examination of the containment liner revealed no bulges.
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The inspector has no further questions or comments on this item.
7.
ROIR 74-2. "PWR > bin Stems Line Isolation Valves" DPC's response, dated March 5, 1974, to Regulatory Operations Information Request 74-2 was verified by the inspector.
Oconee 2 does not have steam isolation valves, therefore, this iten is not germar.e to Oconee 2.
8.
High Energy-Line Break Modifications
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The schedule for completing the high energy-line break modifications was discussed with licensee management.
Management stated that Unit 2 modifications will be completed prior to startup from the current outage for pump repairs.
The modifications are described in MDS Report 05-73,2, " Analysis of Effects Resulting from Postulated Piping Breaks Outside Containment,"
dated April 25, 1973,- and Supplement 1, dated June 23, 1973, i
This item will be carried as an unresolved item pending followup by Region II on co=pletion of the work.
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