IR 05000302/1973013
| ML19319D009 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 01/03/1974 |
| From: | Crossman W, Vallish E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19319D000 | List: |
| References | |
| 50-302-73-13, NUDOCS 8003040936 | |
| Download: ML19319D009 (12) | |
Text
{{#Wiki_filter:- . 3(v , .
- " %
I UNITED STATES 'q ATOMIC ENERGY COMMISSION , e D '-
DIRECTORATE OF REGUIATORY OPERATIONS , e .g n E oio n is - suit E sis
. $ 230 PE AC HT REE ST nEET. NORT HWES1" 3 #14rgg 0 AT L ANT A. GEoRos A 30303
, , . . RO Inspection Report No. 50-302/73-13 t Licensee: Florida Power Corporation 3201 34th Street South . P. O. Box 14042 St. Petersburg, Florida 33733 Facility Name: Crystal River 3 Docket No.: 50-302 License No.: CPPR-51 Category: A3/B1 Location: Crystal River, Florida Type of License: B&W, PWR, 2560 Mwt, 885 Mwe Type of Inspection: Routine, Unannounced, Construction Dates of Inspection: December 10-14, 1973 Dates of Previous Inspection: December 5-7, 1973 Inspector-in-Charge: E. J. Vallf ah, Reactor Inspector Facilities Section, Facilities Construction Branch Accompanying Inspector: F. U. Bower,, Reactor Inspector Engineering Sectica, Facilities Construction Branch > Other Accompanying Personnel: None Principal Inspector: [[ h w E. J. Vallish, Reactor Inspectdd, Facilities Date Section, Facilities Construction Branch Reviewed by: h //8/7</ c W. A. Crossman, Senior Inspector, Facilities Section Date Facilities Construction Branch ! l a -
8003040fN
. _ _ . _.. _. _ _ _. _ . _.. -, ry
R0 Rpt. No. 50-302/73-13-2-- - . , - . SUIMARY OF FINDINGS s . I.
Enforcement Action < '
A.
Violations ,
. ' None s B.
Safety Items , i 'l Nee . II.
Licensee Action on Previously Identified Enforcement Matters '
- ' . A.
Violations
73-1/A2 Decay Heat and Makeup and Purification Systems Radiography , ! ! The licensee has identified the deficiencies in radiographic , j inspection. A corrective action program has been approved and is starting to be implemented.
This item remains open.
i B.
Safety Items None i III. New Unresolved Items 73-13/1 Inadequate Wiring Devices i The wiring gutters associated with control room entry ports 54A & 54B appear inadequate for the intended purpose.
(Details II, paragraph 5.a) 73-13/2 Cabinet Wiring Channel Separation i Redundant channel separation techniques for "in-cabinet" wiring appears inadequate.
(Details II, paragraph 5.b) t .
. IV.. Status of Previously Reported Unresolved Items 73-11/1 Sea-Water Discharge Pipe Joints ' Ths architect engineer is performing an engineering analysis ~ on the design of these joints to determine if an omitted weld
~ bead will effect safety. This item remains open.
s l . I - i .... _.. _ - .- . -.. - .--.- -, . - .,.. -,...... . - - , -...,,, -.... _... - -
- - - _.
~. . . ._ . . " rw
, R0 Rpt. No. 50-302/73-13-3-
. .
. , 73-5/2 Safety valve Piping i - ' . i Assurance is required that safety valve piping design criteria did include dynamic force reactions. The licensee is obtaining an engineering.avaluation. This item remains open.
' - ! -- i 73-5/3 Valve Wall Thickness Requirements t .. In response to the RO:II letters of June 30, 1972, and
February 16, 1973, the licenses has developed a valve wall
l thickness verification program. This item remains open.
' 73-5/5 Control Rod Drive (CRD) Undervoltage Trip Assembly Deficiency, The deficient assembly has been modified as planned.
This i item is closed.
(Details II, paragraph 3) ' ! 73-5/12 FPC Audit of B&W . l \\ j The results of the FPC audit of B&W were reviewed with regard
to scope, depth, findings, follow-up action and results.
This ' ! item is closed.
(Details I, paragraph 3)
73-5/14 Reactor Internals Modification i Modification to these internals is being accomplished in the vendor shops prior to delivery to the site.- This item remains open.
.
, l V.
Design Changes None VI.
Unusual Occurrences None VII. Other Significant Findings i Regulatory Operations Bulletin.No. 73-2 The licensee has analyzed the - condition as it relates to Crystal River - Unit No. 3 and concluded that they are protected against the reported
type failure. This item is closed.
(Details II, paragraph 4) I VIII. Management Interview
i A.
On December 12, 1973, the inspectors met with'E. E. Froats, Manager - Site Surveillance; C. E. Jackson, Construction Superintendent, and y others of the staf f, and discussed the scope and results of the inspec-tion. No violations were identified.
. ' .-. -. _ .- - - - - . ..- - - -
. - -. - ~ - _ -. -.. -.... .. __- ... - - -... .. . _ _ _ _ _ _ _ _ _ i
- t a
-
e,
30 Rpt. No.'50-302/73-13 ~4-
. . B.
On December 14, 1973, E. J. Vallish met with M. H. Kleinman,
Director, Generation Quality and Standards, and discussed the
i results of the review of the FPC audit of B&W.
! . -l '
i i e I i i , . . i .!
.
I . . i i
l
I ~ i
l t
. l $ I
, . I ! ! , ! . ! ' , O e i ..... _.. _. __.__ ., _.... _.. _.. _.. _ _ _.. ... .... . . . . . . , _. _ _
-. - _ _ _ _ - _ - _ _ _. _ _ _ _ _ _ _ ___-__ <. , ,, %_ ( ) RO Rpt. No. 50-302/73-13 I-1 ' - . DETAILS I Prepared by: [ cr & + e / 7Y E. J. Vallish, Reactor Insp4ctor 'Date Facilities Section, Facilities Construction Branch . Dates of Inspection: December 12-14, 1973 - ' /78 Reviewed by: eh W. A. Crossman, Senior Inspector Date - Facilities Section, Fe,ilities Construction Branch 1.
Persons Contacted Florida Power Corporation (FPC) . M. H. Kleinman - Director, Generation Quality and Standards E. E. Froats - Managet, dite Surveillance C. E. Jackson - Construction Superintendent R. W. Slater - Quality Engineer N 2.
Personnel Changes None significant to this inspection.
, 3.
FPC Audit of B&W (Unresolved Item 73-5/12) A.
These documents were reviewed: 1.
"FPC Generation Quality and Standards Department Audit of Babcock and Wilcox Company."
2.
" Quality Assurance Program Audit of FPC Contractor B&W Nuclear Power Generation Division (NPGD); Lynchburg, Virginia, September 12-15, 1972."
3.
" Quality Assurance Program Audit of FPC Contractor, B&W Nuclear Equipment Division (NED); Barberton, Ohio, November 28 - December 1, 1972."
4.
B&W's reply to both NPGD and NED audits, dated April 20, 1973, from C. E. Barksdale, Project Manager - B&W to W. A. Szelistowski, Director - Generation Engineering, FPC.
5, Evaluation of B&W response to the September 1972 NPCD and Os November 1972 NED audits, from W. G. Warwick, G-E Apollo and Ground Systems; to E. E. Froats, FPC, Manager - Site Surveillance, FPC; dated July 10, 1973.
. _ _ . __ .. ....
--
' -
/' RO Rpt. No. 50-302/73-13 I-2 . - . . . 6.
B&W responses to FPC comments to B&W responses to the FPC , Quality Assurance Audits of NPGD in September 1972, and NED. in November 1972; from C. E. Earksdale, Project Manager, B&W; to M. H. Kleinmac, Director Generation Quality and Standards, FPC; dated August 24, 1973.
. . 7.
"FPC follow-up audits of B&W NPGD," dated October 16-18, 1973.
8.
" Status of Findings," dated October 18, 1973.
. , . B.
The review of the results of th.: FPC Audit of B&W NPGD and NED, and of the ensuing correspondence considered the results with . respect to scope, depth, findings, follow-up action and results.
There were no deficiencies revealed.
FPC upper management has-reviewed these reports. Examination of FPC's rationale concerning an audit of the management of the B&W Construction Company revealed no deficiencies and the unresolved item 73-5/12 is considered, closed.
. M
< e e -_
___ . -- _ _ _ _ _ _ _ _ _ _ _ - _ _ _ - .- . CN RO Rpt. No. 50-302/73-13 II-l . [2-7h DETAILS II Prepared by: enfM.
- F. U. Bower, Reactor Inspector Date Engineering Section, Facilities ~ Construction Branch ' Dates of Inspection: December 10-12, 1973 - Reviewed by: /f-1h* J . Bryantfdienior Inspector Date - ineering Section, Facilities - Construction Branch.
1.
Persons Contacted a.. Florida Power Corporation (FPCS R. Slater - Quality Engineer . G. Walker - Electrical Engineer, Construction A. Comez - Electrical Control Systems Manager J. Hobbs - Mechanical, Electrical Superintendent R. Bonner - Electrical Engineer b.. Contractor Organizations E. C. Ernst Co.
A. Brewton - Electrical Supervisor, Cables , 2.
Electrical / Instrumentation (E/I) Construction Progress E/I construction is estimated to be 65% complete and basically on schedule. Work is progressing satisfactorily in the turbine-generator building, control room and the auxilliary building.
Little work has been performed inside the reactor building and r.reas immediately adjacent.
Cable installation is being tracked very closely and progress computed on a daily basis. Work in these areas is presently 48% complete, consisting of 1,497,000 feet of cable pulled of an estimated total of 3,160,000 feet for the total project.
The total number of cables pulled is 7513 of which 720 are safety related.
Conductor termination work is well advanced and is estimated to be 36.2% complete.
This estimate comprises 51,858 t.erminals made of a total expected of 143,163.
N There were no known current problems that are expected to impinge upon ) the completi,on program.
. l . - _J .n
.. -. . , ~, ' RO Rpt.'No. 50-302/73-13 II-2 , ,
. 3.
Previously Reported Unresolved Items Control Rod Drive (CRD) Undervoltage Trip Assembly Deficiency (735/5)' '
The NSSS contractor analyzed the information available regarding the , . subject deficiency and concluded that the marginal coils must be changed.
- The A&E concurred in this evaluation. The redesigned coils, as supplied , by the original device vendor, were installed and tested as set forth in ' , detail by an Engineering Change Notice. These modifications vere made by the original fabricators and were inspected and approved by the site QC - inspection unit.
. All of the above documentation was examined by the inspector.
No deficiencies were identified.
This item is closed.
j 4.
Other Significant Findings ' . Regulatory Operations Bulletin No. 73-2 - In response to an RO:II letter (July 13, 1973) requesting action regarding the possibility of a similar problem at the Crystal River project, the ' licensee has responded (in part) with the following information relative s to the system in question.
"AHV-1A and AHV-10, the outside Reactor Building Containment Purge ' Valves, are operated by dual solenoids which are energized to open and fail closed.
In the event that a switch contact block would fail causing the valves to remain energized and an RB isolation - signal was initiated, the valve would close since the RS isolation signal is in series with the switch and opening the circuit anywhere causes the valve to close.
In addition, there are local pushbuttons near the valve to open or close the valve if required.
The normal switch is located on the ES section of the control board."' ... The response continues. . .. "AHV-1B and AHV-1C, the incide Reactor Building Containment Purge Valves are operated by motor operated valves.
If the switch be-comes defective, thus preventing closure of the valve, two alterna- ~ - { tives are left.
If a containment isolation signal is initiated, ) this circuitry bypasses the switch and will close the valve.
In J addition, there are pushbuttons located at the motor control center i to close the valve."
l "In summary, we are protected against this type of failure at Crystal Rivar Unit No.
3."
The evaluation presented above was reviewed and the conclusion reached is shared by the inspector..This item is closed.
! . . -., --. . -. . - -, ... .. ._ - - _. -,
- _ :;
-~,
_ _ _ _ _ _ . . , y% RO Rpt. No. 50-302/73-13 II-3 . - . 5.
New Unresolved Items
. a.
Inadequate Wiring Devices ~ . j The terminal boxes serving control. board sections ESF(A) and ESF(B) . have wiring gutters that seemingly are of inadequate-capacity for ' the cables entering'from the floor entry ports insnediately below.
(Ports 54A & 54B) ' ' . Site engineering has agreed to examine these wiring devices and
' others with similar potential problems and take corrective action-where needed as revealed by the examination.
b.
Cabinet Wiring Channel Separation- ' ' Examination of a number of the control room cabinets which included engineered safeguards systems (ESS) test panels 2, 2A, '13, 3, 3A and 3B, as well as other boards located in the control room, ladt-cated to the inspector that the single failure requirements set
i forth in IEEE 279 may not be fulfilled by the internal cabinet wiling i techniques ut1lized.
Specific reference is made to the apparent wide ~ use of teflon tubing, placed over the insulation of individual con- , ductors, as the principal means of providing a " barrier" between con- ' ductors of opposite and redundant ESS channels.
From the generar observation made by the inspector, it appeared that
j for inter-cabinet wiring, large numbers of coaductors representing ! all categories of conductors generally requiring separation by space and/or barrier were laced into the some bundle with only the teflon
i tubing between.the opposite channel conductors.
Cables and conductors entering the cabinets from an external source appear to have been handled in a more circumspect r.anner but there were items that see a-ingly fitted into the same category.
, The applicable procedure covering such installations was examined and discussed at length with several responsible members of the site ' staff.
Results of these discussions were inconclusive in the sense ! that evaluation of the intent of the procedure, as it relates to the f use of teflon tubing, seemed to be polarized at opposite positions.
Additionally, the inspector questioned the value of teflon tubing
for any such purpose as providing a barrier in an accident environment j within the cabinets.
As an interim action item, the responsible site ' engineer agreed to examine these installations with the inspector's } evaluations of ' their procedure and his. discussion of the requirements i on the subject in mind.
The inspector also will seek information and j guidance on this subject from internal sources. A course of action ' will be determined prior to the next inspection that should lead to , l, ultimatt resolution of this item.
, , . ' _ .., - _- -, - - -. ~ -- - ~ ~ ' ~ '~*' ~""***~ ~
- _ _ ..-- _.
_ ^ RO Rpt..No.. 50-302/7..3 II-4 (<- , . 6.- faspection Results
- , The following listed equipment and cables were examined as representative , ' samples of installed safety related systems.
This equipment and related QC documentation was inspected for such' features as workmanship, handling techniques, protection of installed equipment, cleanliness, QC inspection and documentation, and requirements of licensing such as redundancy, . ' physical separation, structural integrity, material certification, testing, -. use of proper materials and the suitable implementation of the QA/QC program.- F a.
Reactor building spray system, isolation valve operators,: BSV 3 & BSV 4.
. b.
Reactor building spray't umps control cables BSM2 & BSM8. Apart from the unresolved item previously discussed herein, the subject examination of the abov'e 11. ted equipment and materials did not reveal deficiencias.
' Inspection of instrumentat. ion systems marked for examination was deferred until some such future time that representative samples of equipment have been installed within the reactor building.,
, 7.
Miscellaneous Items . a.
Battery Rack Documentation The FPC letter, to be placed in the related QC file, that confirms the battery rack seismic calculations and design was examined by the inspector and found suitable for its intended purpose. No deficiencies were identified.
This item is closed.
b.
Baily Meter Seismic Documentation Information updating the status of the subject materials was presented informally to the inspector. Progress towards completion of this task was implied with positive results to be confirmed by the next inspec-tion in this area.
l c.
Construction Drawing Error
The construction drawing identified and discussed in RO:II report 50-302/73-7 as potentially in error was informally discussed. The staff reported that the drawing had been determined as ae least misleading, if not in error, by FPC and action is being taken to change it.
This item is closed.
8' Cable Spreading Room . ' The cable spreading room was examined to observe the continuing progress of the corrective action initiated following the inspectors comments contained in RO:II 50-302/73-5. Discussion with the site staff indicated that' the work originally ant 1cipated to make the needed changes proved to ' be underestimated when compared to what has and is being accomplished.
. t-t- , .._ .m
" r .. * 9 r .. ,m - RO Rpt. No. 50-302/73-13 II-5 . . , In addition to the need to evaluate the access ports to the racks above for size and location and the re-routing of several hundred - cables required due to this evaluation, it has been found necessary to add approximately 75 additional trays, raceways and conduits to provide the degree of separation required by the applicable procedure.
- . Inspection of the area indicated a much less confused picture than had been previously the case.
The work now shows a greater degree ' of order and improved workmanship.
- , . . i
1
i ) l _ . . . . - -. . _
- - - ,- , . . . Letter to Florida Power Corporation dated 50-302/73-13 . - . ~ DISTRIBUTION: M. D. Thornburg, RO ' RO:HQ (4) ) Directorate of Licensing (4) - DR Central Files -)
- PDR
]
- Local PDR
- "NSIC
- DTIE, OR
- State
- To be dispatched at a later date.
O -- . }}