IR 05000269/1972010
| ML19322A644 | |
| Person / Time | |
|---|---|
| Site: | Oconee |
| Issue date: | 01/15/1973 |
| From: | Jape F, Murphy C, Warnick R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19322A641 | List: |
| References | |
| 50-269-72-10, NUDOCS 7911210710 | |
| Download: ML19322A644 (29) | |
Text
{{#Wiki_filter:. UNITED STATES h ~ 'g(1} , ' -g"# ATOMIC ENERGY COMMISSION % -,'. e J - DI?2CTO? ATE OF F23ULATCRY CFI?aTIC::S lJ Recion n - suit E sie . 230 P E ACHT R E E ST R E ET. NC8tT H WEST , ,,,, If4FE5 C* AT t. A N T A, CEoRGI A 30303 RO Inspection Report No. 50-269/72-10
Licensee: Duke Power Company , Power Building 422 South Church Street Charlotte, North Carolina 28201 Facility: Oconee Unit 1 Docket No.: 50-269 ' License No.: CPPR-33 Category: B1
Location: Seneca, South Carolina Type of License: B&W, PWR, 2452 Mw(t) Type of Inspection: Routine, Unannounced , , Dates of Inspection: November 14-17, 1972 Dates of Previous Inspection: October 3-6;-1972 Principal Inspector: R. F. Warnick, Reactor Inspector Facilities Test and Startup Branch Accompanying Inspector: F. Jape, Reactor Inspector Facilities Test and Startup Branch Other Accompanying Personnel: None " Principal Inspector: .kW?9 /
R. F. Warnick, Reactor Inspector ' date Facilities Test and Startup Branch Reviewed By:..- M ///>
C. E. Murphy,fAcring Chief / Date Facilities Test and Startup Branch l l 7911210. 2 / O -- . .. , i i
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-2- .., SUMMARY OF FINDINGS " l I.
Enforce =ent Action None II.
Licensee Action on Previously Identified Enforcement Matters , ! f A.
Violations . , .
The following items are closed: I 1.
Control of Lifted Leads and Electrical Jumpers (See letter ' to DPC dated March 8,1972, Item 7.)
e ! DPC will make cable termination checks for certain portions I of the engineered safeguards systems and the reactor pro-tective system. This item is closed.
(See Details I, paragraph 2.)
i i 2.
Criterion VI - Failure to Distribute Welding Procedures i l to Craf t Personnel or QC Field Engineers (See letter to DPC dated October 26, 1972, Item 3.a.)
' > The procedures have been distributed and site personnel . instructed relative to timely distribution. This is closed.
(See Details II, paragraph 2.)
i 3.
Criterion VI - Failure to Obtain Proper Approval for Test Procedure (See letter to DPC dated October 26, 1972,
Item 3.b.)
The controlling procedure for conducting hydrostatic l tests was approved by the plant superintendent. This item is closed.
(See Details II, paragraph 3.)
4.
Criterion XVI - Failure to Identifiy and Report the Cause - of Weld Defects (See letter to DPC dated October 26, 1972, Item 7.)
Specific reporting instructions have been given and the defects have been corrected.
This item is closed.
(See Details II, paragraph 4.)
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- 5.
Criterion XVIII - Failure to Conduct Effective Audits of Electrical QC Activities (See letter to DPC dated ,
October 26, 1972, Item 8.)
f Additional audit has been performed and the results j reviewed by RO.
This item is closed.
(See Details I, , j paragraph 3.)
, ' . The following items remain open: 6.
Welding Program Deficiencies (See letter to DPC dated March 8, 1972, Item 5.)
DPC stated that their final report on welding deficiencies and improvements in their welding program should be avail-able af ter December 25 for AEC inspection.
7.
Criterion V - Failure to Implement Approved Procedures for Control of Nonconforming Items (See letter to DPC dated October 26, 1972, Item 1.b.)
- Response to letter received.
Corrective actions will be examined during subsequent insp(ction.
, 8.
Criterion VII - Installation of Cable Without Documenting Evidence that Cable Met Frocurement Specification.
(See letter to DPC dated Octohar 26,19 72, Item 2.)
Response to letter received.
Corrective actions will be examined during subsequent inspection.
t 9.
Criterion VI - Major Changes Made to Test Procedure Handled as Minor Changes (See letter to DPC dated October 26, 1972, Item 3.c.)
The definitions of tajor change and minor change are still - being discussed.
10. Criterion VI - Failure to Document changes to Test Pro-cedures (See letter to DPC dated October 26, 1972, Item 3.d.)
Additional instructions have been given and this item will be reviewed during a subsequent inspection.
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_ _ _ ie . , . , -~ _4 11. Criterion XIV - Failure to Es'tablish Measures to Indi-cate the Status of Cable (See letter to DPC dated October 26, 1972, Item 4.)
- Response to letter received. Corrective actions will be examined during subsequent inspection.
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12. Criterion XI - Failure to Document the Results of a Test (See letter to DPC dated October 26, 1972, Item 9.)
Additional instructions have been issued by DPC and this item will be reviewed during a subsequent inspection.
B.
Safety Items None III.
New Unresolved Items . None IV.
SJ . Previousiv Reoorted Unresolved Items The following items are closed: 1.
Reactor building spray pumps have been tested and the vi-bration problem corrected. This item is closed.
(See Details II, paragraph 5.)
2.
The seismic monitoring system has been reviewed and is in agreement with the FSAR. This item is closed.
(See Details I, paragraph 4.)
3.
Containment and auxiliary building ventilation system filters test will be completed as described in Test Procedures 115/1, . 161/3, and 161/4 which have been reviewed by RO:II. This item is closed.
(See Details II, paragraph 6.)
4.
The air receiver has been isolated by a concrete block wall.
The air line has been rerouted.. The safety valves will be tested. This item is closed.
(See Details I, paragraph 5.)
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- { B&W has evaluated the results of using hydraulic snubbers in the reactor coolant system flow sensing lines and finds i them acceptable. This item is closed.
(See Details I, paragraph 6.)
6.
Inspection of fuel assemblies prior to initial fuel loading { will be completed as described in Oconee procedures. This
' item is closed.
(See Details II, paragraph 7.)
. 7.
A demonstration of the station PA system to ensure audibility at all locations in the plant will be completed prior to ! fuel loading. This is described in procedure TP-361/01.
f This item is closed.
(See Details II, paragraph 8.)
8.
The operational quality assurance organization, as described in DPC's " Administrative Policy Manual for Operational Quality Assurance of Nuclear Stations," is independent of the station operations organization. This item is closed.
, ! (See Details I, paragraph 7.)
9.
The procedures for receiving, storing, and shiorfre fuel assemblies have been revised to include instru.21ons regarding criticality control. This~ item is closed.
(See Details II, paragraph 10.)
The following items remain opta: - 10. Verify by startup test that the reactor prote ction system responds to axial power icbalances in a mannor designed to prevent the axial itsign peaking factor f; om being exceeded.
RO is waiting to receive a copy of procedure TP-800/24 for review.
11. Verification of core bypass flow - RO is waiting for a test ' to be identified and a procedure to be writt en to verify core bypass flow.
12. Remove reactor internals and inspect for evidence of fretting, wear, and cracks after completion of preopecational tests - RO received procedure TP-200/22 and will review.
13. Conduct field tests of the steam generator to confirm results of the tests performed on prototype tubes - RO received procedure TP-800/22 and will review it.
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. . B-6- . 14. Reactor coolant pump flow tests to verify design flow rate and coastdown flow rate - RO received procedures TP-200/12 and TP-200/13 and wil1~ review.
15. Reactor internals vibration test - RO is waiting to receive and review the test procedure.
~ 16. DPC indicated they will visually inspect reactor coolant
piping and equipment for vibration.
- RO is waiting to receive a test procedure for review.
Par-ticular concerns are checksheets, acceptance criteria, and when the test will be conducted.
17. The results of DPC's ultrasonic measurement of wall thick-nesses of valves within the reactor coolant system pressure boundary should be available for RO review af ter December 1, 1972.
18. Verify loop backflow analyses by tests on reactor coolant loops - RO will review the test procedure when it is available.
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19. Flow meter error analysis and cests 4 RO is awaiting information and action from DPC concerning this item.
20. A draft copy of DPC's proposef eperational quality assurance manual was obtained for revief-21. DPC is going to rerun the reactor coolant flow tests during the testing sequence which will follow the modifications of the reactor vessel internals.
22. Seventeen radiation protection, environmental monitoring, and radwaste system commitments have not yet been met.
These will be inspected in December.
- V.
Desian Changes None VI.
Unusual Occurrences None . owe =esme w _. eseg p.
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Other Significant Findings
None . VIII.
Management Interview A management interview was held on November 17, 1972, at the con-
, clusion of the inspection. The following people w' ire in attendance: ' - Duke Power Company (DPC) I J. E. Smith - Plant Superintendent J. W. Hampton - Assistant Plant Superintendent R. M. Koehler - Technical Support Engineer E. D. Brown - Maintenance Supervisor L. E. Summerlin - Staff Engineer The following items were discussed: A.
Unit 3 Insoector Assignment Effective this inspection, E. J. Vallish is assigned to be the AEC Region II Principal Inspectof for Oconee Unit 3 replacing R. F. Warnick.
B.
Previously Identified Enforcemtat Matters The status of previously identified enforcement matters, as described in the summary of findings, was discussed.
C.
Previously Reported Unresolved Items The status of previously reported unresolved items, as described in the summary of findings, was discussed.
D.
Operational Quality Assurance Manual ' The inspector acknowledged receiving a draf t copy cf DPC's " Administrative Policy Manual for Operational Quality As-surance of Nuclear Stations" (Operational QA Manual) for in-office review and stated that comments would be discussed during the next inspection. At the conclusion of the review, the manual will be returned to the licensee.
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. _ i . -8- . The inspector stated that the three administrative instructions, which have been incorporated in the operational QA manual, were reviewed, comments discussed, and agreement reached on all comments.
(See Details I, paragraph 9.)
DPC concurred with the above.
- E.
Operational Quality Assurance Audit - ' The inspector stated that he had reviewed DPC's report of ' their first operational quality assurance audit and that the findings of the audit were consistent with the findings - of similiar AEC audits. No deficiencies in the audit pro-cedure or report were noted by the inspector.
(See Details I, paragraph 3.)
F.
Steam Generator 1A Tube Leak ! The inspector indicated he had reviewed this matter and had ! no further questions at this time. (See Details I, paragraph 8.)
. G.
Operating Procedures Review ! The inspector stated that five operating procedures out of a total of 88 had been reviewed.. Comments on two of five procedures were discussed and resolved with the licensee's management.
' RO has no questions on the ot'aer three operating procedures that were reviewed.
(See Details II, paragraph 9.)
H.
Fuel Handling Procedures The procedures for shipping, receiving, and inspecting fuel assemblies were reviewed. These procedures have been revised since the previous inspection and all previous questions have been resolved.
(See Details II, paragraph 10.)
I.
Zero Power Physics Test (ZPPT) Procedure - The ZPPT procedure was reviewed. Questions on this procedure were discussed and resolved with the licensee's representatives.
(See Details II, paragraph 11.)
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' , . I-1 DETAILS'I Prepared By:.[[ N. 2 L. ( N ./ * R. F. Warnick, Reactor Date - Inspector, Facilities Test and Startup Branch Dates of Inspection: November 14-17, 1972 Reviewed By: [ '- * ' -f ~ /- " ' ) C. E. Murphy, Acting Chief Date
Facilities Test and Startup Branch 1.
Individual Contacted A.
Duke Power Cocoany (DPC) R. L. Dick - Vice President, Construction W. H. Owen - Vice President, Design Engineering W. O. Parker - Assistant Manager, Steam Production Department K. S. Canady - Nuclear Engineer D. C. Holt - Assistant Nuclear Test Engineer J. E. Smith - Plant Superintendent J. W. Hampton - Assistant Plant Superintendent R. M. Koehler - Technical Support Engineer O. S. Bradham - Instrument and Controls Engineer D. G. Beam - Project Manager, Construction D. L. Freeze - Principal Field Engineer C. B. Aycock - Senior Field Enginear K. W. Schmidt - Associate Field Engineer, Electrical D. D. Brandt - Test Technician W. H. Knight, Jr. - Utility Operator B.
Contractor Oreanizations Babcock and Wilcox Comoany (B&W) W. Faasse - Site Construction Manager ' ' 2.
Lifted Leads and Jumoer Control To provide assurance that the results of earlier preoperational tests have not been negated by inadvertent or unknown lifted leads or mis-placed electrical jumpers, DPC has agreed to perform a 100 percent termination check for control cable for the engineered safeguards porticas .. . , pgg,%, .p .*w, _-,-**7***N*P
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I I-2 - . , ~.. tions of the high pressure injection system, the low pressure injection system, the reactor building spray system, the reactor building isola-tion system, and the reactor protective system. This review will not ~ include individual component ends of cable nor the power switching circuitry.
i i DPC informed the inspector that all cabinets have been checked for tem-porary jumpers and that all have been identified per MP-1400/20, Oconee ' Nuclear Stations " Electrical Interlock and Circuit Bypass Procedure."
. . The results of DPC's inspection of the engineered safeguards and reactor protection circuit terminations will be reviewed when available. At this time, RO:II has no further questions and considers this item resolved.
! Quality Assurance Audits -/
3.
On November 8, 9, and 10,1972, nine design, construction, and staff engineers from offsite conducted an in-depth audit of the Oconee Nuclear Station construction quality control in the mechanical, civil, and electrical areas. The audit was conducted according to a written j procedure which included checklists. It covered organization, pro- .' cedures, documentation, and field verification.
The RO inspector listened to the conference phone call report of the
electrical audit findings to the site const uction and QC management.
! The inspector noted the extent and the detail of the audit and observed , that the audit findings were consistent with the findings of similar l AEC audits.
.. I On December 7,1972, DPC confirmed by telephone that the audit results , ! had been reported in writing and that corrective actions were being l taken and would be documented.
' The inspector also reviewed the report of an operational quality as-surance audit performed by three members of DPC's corporate staff on October 19 and 20, 1972. This was the first operational quality as-surance audit performed at Oconee. The audit was conducted in accord-ance with a predetermined inspection outline. The outline defined the.
items to be audited, the audit prerequisites, the forms to be used
in documenting the audit results, and the audit procedure.
i 1,/ See RO Inspection Report No. 50-269/72-8, Section II, paragraph 12.
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I The audit report docu=ented the findings of the auditors. The audit iv.luded items which have been inspected.by the AEC during the past ' v ar.
The findings of DPC's audit team were consistent with the findings l of previous AEC audits.
i I Areas audited included flow diagrams, shift supervisor's logbook, FSAR testing requirements, unusual condition reports, and preoperational ' -
test procedures.
4.
Strong Motion Accelerometers Oconee Unit I will have two self-contained strong motion recorders which start recording on.Olg motion and record continuously for seven l seconds. Calibration and battery checks will be made quarterly. The } inspector observed one unit mounted on a concrete pedestal in the ' tendon gallery. A second recorder will be counted in the reactor ! building and will be identically oriented.
l The inspector observed a small unit, referred to as a seismic trigger, l mounted on the concrete pedestal in the tendon gallery.
It actuates ! a control room alar = annunciator at.05g.
l An instrument test technician informed the thspector that Unit 1 will j have six self-contained peak recording accelerometers, model PRA-103.
One was observed in the tendon gallery. The other five were not inspected.
.- The inspector reviewed the strong motion accelerometer calibration procedures, TP-125/1 and TP-125/2. The inspector also reviewed correspondance from Teledyne - Geotech of Garland, Texas, the manu-facturer of the equipment, regarding calibration instructions for the instruments installed at Oconee station.
t l No deficiencies were noted in the calibration procedures and instruc-I tions. The inspector has no further questions.
- 5.
Control Air System The inspector observed that the air receiver has been isolated from l the batteries and the air line has been rerouted out of the battery room. The receiver can be isolated from the control c!,r system to , ! 1,/ See R0 Inspection Report No. 50-269/72-4, Sectier II, paragraph 4.
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l . , . ,. I-4 . make it available for maintenance. On December 6, 1972, me=bers of DPC management stated that the safety relief valves will be tested at least every three years. This item is closed.
- 6.
Use of Snubbers in Reactor Coolant Flew Instrumentation 1/ - The use of snubbers in the reactor coolant system flow sensing lines - has been justified by B&W.
(See Exhibit A) This item is closed.
7.
Independence of ooerating Quality Assurance Organization A draf t copy of DPC's " Administrative Policy Manual for Operational Quality Assurance of Nuclear Stations" was obtained for review in the regional office. Figure. 4-2 shows that the Staff QA Engineer reports to the Steam Production Department /ssistant Vice President for matters pertaining to operational quality assurance (He has no other duties.) although for administrative purposes he reports to Manager, Operations and Maintenance. The Nuclear Station Suoerintendent reports to the Steam Production Department Assistant Vice President. This independence of the corporate QA organization from the nuclear station operations organization was confirmed by the Steam Production Department Assistant Manager. This item is closed, s 8.
Steam Generator lA Tube Leak On Octobe142,1972, J. W. Hampton informed the inspector by telephone that during a 1000 psig hydrostatic pressure test of the A steam generator for Unit 1, a tube leak was discovered. The leak rate was measured at approximately one cup per minute.
The section of tube containing the leak was removed for examination and analysis. The leak was reported to be in a circumferential crack located approximately 1/3 inch above the top side of the bottom tube sheet.
Previous to this test, the B steam generator for Unit 1 had been - given a successful hydrostatic pressure test (following the repair of three top tube sheet tube weld leaks).
1/ See RO Inspection Report No. 50-269/i2-7, Section II, paragraph 10.
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. ., . The inspector was informed that 1000 tubes in steam generator 1A and 1000 tubes in steam generator 1B had been Eddy current tested over their entire tube length.
In addition, more than 1000 tubes were given an Eddy currcat inspection one-inch below and two-inches above the top of the bottom tube sheet. The three-inch zone in certain of these tubes was also given an ultrasonic inspection. The results of the tests were not available. They will be reviewed during a subsequent inspection.
. 9.
Administrative Instructions The inspector discussed R0 comments on three administrative instruc-tions which will be incorporated in the 'Hanual for Operational Quality Assurance." The comments and resolutions are as follows: DPC will include an exception for Oconee Units 1 and 2 ;d allow a.
for the existing practice of delegating authority to the Operating Engineer and the Technical Support Engineer to approve certain hydrostatic test procedures and chemistry equipment test proce- , I dures which are governed by a controlling procedure which the Plant Superintendent has approved.
' b.
DPC will revise the definitions of major and minor change.
It was stated that any deficiency ident(fied during a preopera-c.
tional test would be documented and that corrective action would I { be initiated through the " work order" system or through the " resolution of discrepancies."
, d.
DPC will provide words to cover the situation where approvals to test procedure changes are needed during off-shif ts.
Approval ' by phone will be permitted with subsequent documentation of the oral approval.
, ! DPC will include a requirement that test results will be reduced e.
to meaningful and understandable form.
I s i f.
DPC will consider specifying a frequency for review of maintenance; ! periodic, and instrumett procedures.
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DPC will specify that one copy of outdated procedures will be saved for five years as required by the Technical Specifications.
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_ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . II-1 ,s DETAILS 11 Prepared By: /w?4 f, t > O /' fM F. Jape, Reactog/ Ins $ector Date Facilities Test and Startup Branch Dates of Inspection: November 14-17, 1972 f<h~e'/- ',?./. -, ' / A o: -
Reviewed By: / C. E. Murphy, Acting Chief Date Facilities Test and Startup Branch 1.
Individuals Contacted Duke Power Comoany (DPC) J. E. Smith - Plant Suoerintendent J. W. Hampton - Assistant Plant Superintendent K. S. Canady - Systems Nuclear Engineer R. L. Dick - Vice President, Construction W. O. Parker - Assistant Manager Steam Production W. H. Owen - Vice President, Design Engineer T. McConnel - Engineer S. Holland - Relief Shift Supervisor R. M. Keohler - Technical Support Engineer R. Wilson - Performance Engineer, Unit 1 G. W. Cage - Assistant Operating Engineer L. E. Summerlin - Staff Engineer 2.
Failure to Distribute Welding Procedures "to Crdf t Personnel c*r OC Field Engineers 1/ All revised welding procedures were issued to the field forces on September 1, 1972, by the Associate Field Engineer-Welding in accord- ' ance with DPC's QA :rocedure G-1, " Procedure for the Control of Documents.
1/ See RO Inspection Report No. 50-269/72-8, Section III, paragraph 2.
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. . . . . . . , II-2 '. ,. DPC prepared, approved and issued on October 3,1972, a QA procedure L-97, entitled " Welding Program, Oconee Nuclear Station." Section 5 of the procedure, entitled "Implecentation," requires the welding in-spectors and welding foreman to receive training on interpretation and understanding welding procedures.
. i The welding procedures are now under the control of the QA program . and are issued in accordance with QA procedure G-1, " Procedure for
' the Control of Documents."
l ! This previously identified item of noncompliance is now closed.
I j 3.
Test Procedure Aooroval Ddlegatied 1/ s The " Administrative Instructions for Preoperational Procedures" were reviewed. 'the definition of an approved test procedure was discussed with the licensee's representatives. The definiticts will be revised i to allow approvals of subprocedures nrovided the controlling procedure is approved by the Plant Suoerintendent.
This previously identified item of noncompliance is closed.
the Cause c f Weld Defects $/ 4'. Failure to Identifv and Reoert DPC's QA procedure E-1, "The Identification and Control of Field Fab- - rication Pipe and Welds." requires the radiographic reviewers (Level II per SNT-TC-1A) to fill out the evaluation portion of fera QC 30, " Radio-graphic ~ Inspection Report," and at the end of the shift to summarize , his findings on QC-61, " Radiographic Inspection Su= mary."
The Associcte Field Engineer-Welding and Associate Field Engineer-NDT are now re-viewing Form QC-61 for serious and repetitive defects and for repairs.
In addition, the welding inspectors have been verbally instructed to J discuss unusual or repeticise defects and repairs with the Associate Field Engineer-Welding. This verbal instruction will be included in DPC's formal training program.
l This previously identified item of noncompliance is now closed.
', I . l i 1/ See RO Inspection Report No. 50-269/72-8, Section V, paragraph.4.b.
2/ See RO Inspection Report No. 50-269/72-8, Section III, paragraph 7.
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Reactor Building Soray Pumo Performance The base and pump modifications to the RBS pump-motor units have been The maximum completed and the vibration problem has been corrected.
1A and 1.3 mils for Unit 1B.
vibration recorded was 0.9 mils for Unit This previously identified unresolved item is considered to be closed.
6.
Containment and Auxiliary Building Vent System Filtrers and * Tests DPC has provided test procedures IP 115/1, " Air Filters Tests High Efficiency Particulate Air Filters," TP 161/3, "RB Purge System Functional and Operational Test," and TP 161/4A, " Hydrogen Purge the System Leak Test," in the preoperational test program to test containment and auxilicry building vent system filters. DPC indi-cated the tests will be completed prior to initial fuel loading.
There are These tests procedures were reviewed by the RO:II inspector.
no questions and this previously identified unresolved item is con-sidered resolved.
s , . 7.
Fuel Insoection DPC has provided miscellaneous test " Final Fuel Assenbly Inspec-2., tion and Spent Fuel Pool Cleaning" and Operating Procedure OP 1503/ 04, "New Fuel Assenbly Inspection and Storage," which will result in a documented inspection of all fuel assemblics scheduled for initial fuel loading for Oconee 1.
These procedures were reviewed by the RO:lI inspector and there are no further questions regarding fuel inspection. This previously identified unresolved item is considered resolved.
8.
Demonstration of PA System Audibility , DPC has provided test procedure TF 361/01, " Evacuation Alarm System Test," in the preoperational test program to test the audibility of the PA system at various locations in the station. DPC indicated the test will be completed prior to initial fuel loading.
There The test procedure was reviewed by the RO:II inspector.
are no further questions, and this previously identified unresolved item is considered resolved.
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Operating Procedures Review ' Five operating procedures were reviewed. These were (a) OP 1102/01, " Controlling Procedure For Unit Startup," (b) OP 1102/04," Power Opera-tion," (c) OP 1102/10, " Controlling Procedure for Unit Shutdown,"
(d) OP 1103/13, "RC System Leakage," and (e) OP 1103/4, "Soluable - Poison Concentration Control."
Comments on OP 1102/04 and 1103/13 were resolved with the licensee's ' representatives. The cocnents on these two procedures are discussed
below. The inspector had no comment or questions on the remaining titree operating procedures.
. In OP 1102/04, blank spaces were discovered in the part of the pro- ' , cedure in which surveillance requirements are prescribed. The licensee's representatives indicated that at the time this procedure was pre-pared, the inforeation to fill the blanks was not available.
Further, it is the'.r plan to fill in all blanka in this and all other procedures as soon as the information and data becomes availabe.
. In OP 1103/13, there appeared to be a lack of detail tegarding the ' plant status during the leak rate determinacion. For example, the ' procedure does not cover the status of makeup, venting, boration or i deboration and chemical additions to the primary coolant system during tae leak rate determination; yet, each of these parameters , ! could hate an effect on the accuracy of the calculation. The pro-
- cedure does not cover equipment status such as changes in pumps and coolers in service or changing the signal sources for pressure, tem-t perature-, level and flow data. A change in equipment status or sig- ' nal source could introduce errors in the leak rate calculation.
. ! The licensee's representatives stated that these comments would be i incorporated into their procedure.
10. Fuel Handling Procedures ' t i DPC's procedures for fuel handling have been revised to include ap- ' havereceivedinstructionsregardingcriticalitycontrol.jpera
propriate comments on criticality control and all fuel han I - During an earlier inspection, it was pointed out that the procedures in i 1/ See RO Inspection Report No. 50-269/72-9, Deta.ls III, paragraph 2.
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s . " . - ., . / II-5 t use at that time lacked this detail. RO has no further questions on these procedures and this previously identified unresolved item . is considered closed.
- 11. Zero Power Physics Test Procedure l The zero power physics test procedure for Oconee 1 has ' aen reviewe'd and comments were discussed with the licensee's representatives.
All of the comments have been resolved and are summarized below: , ! a.
Source Range Nuclear Instrumentation Response Check RO's Comment The source range n clear instrumentation should be checked during the performance of this test. This check is not listed - in the purpose statement nor is there any acceptance criteria given in the procedure for this check.
On page 59 of the procedure, it is stated that the N1 response will be checked as described in IP 301/3K. This instrument procedure is not included in the list of references.
s Licensee's Response The source range nuclear instrumentaion will be calibrated prior ' - to performing the ZPPT and its response will be checked during ' the test. The calibration will be shown as a prerequisite test and the response check will be included in the list of reference tests.
b.
Biological Shield Survev RO's Comment TP 800/3 " Biological Shield Survey" is inclu'ded in the list of - tests and measurements shown on page 9 of the procedure, but the recording of data for this test is not included in the pro-cedure section and no data sheets are included for these data.
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( i II-6 . I i, i Licensee's Response i i i
TP 800/3 is a concurrent test and data will be recorded within
the test procedure during the ZPPT and the power ascension tests. A ' I statement to reflect this will be added to ZPPT procedure.
' , t . ! i e ! Attachment: - . Exhibit A ! i . ! " ,
d I ! ,
. i.
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- . . . .... _ _ _. . . . . .. .. . - BabCOC!( & V!ilCOX pc ,c.n.,,rion oivision P.O. Box 1260 Lynchburg, Va. 24505 October 3, 1972 Telephone: (703) 38 ~.-5111 B72-334 Mr. S. K. Blackley Mr. P. H. Bar on Duke Power Ccepany P. O. Box 2178 f Char 1ctte, N. C.
28201 Subject: Oconee 1 R-40000 Evaluation of Flow Signal - i l Pressure Pulsations l i Gentlemen: Attached for your information is BSW's evaluation of the flow signal pulsations I witnessed during the initial Hot Functional Testing of Oconee 1.
- this information should be sufficient to answer the concerns raised by ccmpliance.
Very truly yours, IN..(f ' % ~/)
4,Z
i R. V. Straub ProjectManager ? IWS/slb Attachments
! CC: G. M. Baccich ! W. Faasse R. J. McConnell
.t .
~' ,,
. l , I ' l- ,V ! ! . i ' ' Exhibit A l ' The Babcock & Wilcon Comcany / Established 1867 - - . _. - _. _.. _ _. _ _.. _. -. _ _ _. _ _. ..
. . .. . ... . .. .~ DUKE POWER CO.',1PANY - GENERAt. CFFICE CHARLOTTE, N. C. 28201 7, - . October 10, 1972 . Mr. J. P. Cifth, Supt.
Cconeo :;uclocr Station . Subject: Ocence Tuclear Statica Evalu.2tien of Flou Sigssl Pressure Pulsatior.s Attached for your inforestien is 37J's evaluation of the flov sinnal ruls.ttiens vitnessed during the initial hot - functior.sl testinn of "c:neo 1.
'T. tis inform. tion chould
han suffi:ic.t t3 en rrer ccacertis by W.C/.A ce. identiflod by ny lo.tter of '.' etcher 9,1972 as outsta.ilne itca f 79 and 133. P1:ssa ra: a this iafo.:;.ation availn51o to the . P.0 insnector uren his next visit.
. K. S. Canady.
'ASC:vr Attachr.ent cc:
- r. U. J. Lark v/o attach.
, "r. J. D.1:ortheuer v/ attach.
Mr. !!. ?!. I'oohler v/ attach.
Tir. D. C. Tolt v/attsc's.
. . l . se P00R BRENAL cm - . ... .- -
. - , :.. .. ,...c,. ,,. . . . .... e . . . . .OCONEE 1 FLOW NETER TRESSURE PULS.\\TIONS r,' 1.
I m 0 DUCTION Initial pt=p testing and hot functional testing at Oconce 1 in late November 1971 and Feb:uary 1972 indicated that the reactor coolant system flow signal was char-acterized by randen fluctuations of approximately one (1) hertz, and of approximately 15% full scale at maxista flow.
Test programs were carried cut to: a) Detemine the cause of the flow signal fluctuations, and b) Determine a correction to the flow signal fluctuations consistent with safety requirements.
2.
SIM RRY OF RESULTS Analysis of the data frem tests at B5W's Alliance Research Center on a mock up of the flow meter instnnent piping system and tests at Oconee in February show that: a.
A relatively broad band of flow turbulence noise exists in the reactor coolant system. The flow tube and the flow instn=ent and piping system respond to and - amplify the system noise in a manner characterized by the gecmetry of the flow tube the length and diameter of the instnmient piping, and the response of the flow , transmitters.
The system noise characteristics were determined by obtaining the power spectral . density (PSD) of several static pressures and differential measurements on Oconce 1.
Figure 1 shows the frequency range and relative signal amplitude envelope for the various measurements, except the flow transmitters, as developed frca the PSD Ana- ' lysis. The frequency range frca approximately 5 h: to 15 h: is that in which the system hydraulic noise occurs. The one hert: flow meter response,(the resonance pe at one h: indicated by the dashed line),then is the characteristic response of the !
flow tube, associated instnnent piping, and the transmitters to the forcing functi
defined by the solid line on figure 1.
l b.
The use of hydraulic snabbing devices in the flow tube instnr.cnt lines was fcund to provide a satisfactory means for conditioning The flow meter signal. A compari- . son of the snubbed flow signal with the unsnubbed flow signal is shown in figure 2.
!
- c.
On the basis of the PSD analysis, it was conc 1uded that the gross system flew is ~ ' stable. The prine factors leading to this conclusion are: a) the absence of any i . ! one resonance frequency ccamon to the individual components of the reactor coolant system. b) Isolating six (6) of seven (7) transmitters on a flow tube cutput sign changes the si;;nal resonance frequency frca approximately one h: to 30 h:, and sig- , nificantly reduces the indicated pulsatien ccaponent of the signal.
! l d.
The hydraulic snubbers in the flow tube instnnent lines cause a time delay in'the j mtput signal. The delay has been analyzed with respect to flow coastdcwn and has
been determined to be acceptable.
, The flux to ficw signal is important for two loss of ficw events: 1) the trip of I ! t ! . .. . - - - -
ee
...-...,,,?.,,,.cn... ... im.. y.. m u. 7.:. - ~,,,,n c.,.,.,... .. ~.,.. g.. . .... l,~.. vvnw, . . ' .. -2- . !. . I one purp frem four pumps initially operating and 2) as a back up signal to the r-i pump nonitor trip signals when two pumps trip from fcur pumps initially cperating.
Figures 3 and 4 shew the estimated flow coastdcta characteristics for mininum syste: + flow under operating conditions for the reacter ecolant punp trips discussed above.
' f (The flow estimates are based en initial HFr data).
Figures 5 and 6 show the respective DNB ratio curves for a trip frem the flux flow signal. The mininum D?.~d ratios are 1.54 and 1.44 respectirely. The ficw recuired to naintain the minimum DNBR of 1.32 is shown by the dashed lines in Figures 3 and 3.
SWmRYONCONCLUSIONS ' The conclusions reached frca the tests and analyses are: , 3.1 Gross system flow is stable.
. i 3.2 The reactor coolant flow measuring system responds to relatively broad band reactc: system noise at the measurement syste-d characteristic frequency.
. 1 3.3 Hydraulic snubbers placed in the flow tube instnnent piping provide an acceptable signal for use in the reactor protection system.
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