ML19261A780
| ML19261A780 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 01/29/1979 |
| From: | Stewart W FLORIDA POWER CORP. |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7902080163 | |
| Download: ML19261A780 (28) | |
Text
049
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[O Q o0Q' a
8 000 Florida Power
- w. e. sTea^a r. o'accroa FOWER PRODUCTION coneonation January 29, 1979 Mr. Robert W. Reid Chief Operating Reactors Branch #4 Division of Operating Reactors U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Subjeep Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72
Dear Mr. Reid:
Your letter of December 22, 1978, requested Florida Pc er Corporation to submit additional information concerning our proposed modification to include Reactor Coolant Pump Power Monitors at CR#3.
Attached for your staff's review are our responses to the two concerns identified in the enclosure of your letter.
It is hoped that our response will satisfy these concerns in order that a timely approval of our request can be granted and the modification complet-ed during our upcoming refueling outage.
Very truly yours, FLORIDA POWER CORPORATION
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P. Stewart ECSekcR02(D4)
File:
3-0-3-a-3 Attachment 7902080 Igg t@
General Office 3201 Tnirty-fourth street soutn. P.O. Box 14042, St. Petersburg, Florida 33733 813-866-5151 f
STATE OF FLORIDA COUNTY OF PINELLAS W.P. Stewart states that he is the Director, Power Production, of Florida Power Corporation; that he is authorized on the part of said company to sign and file with the Nuclear Regulatory Commission the information attached hereto; and that all such statements made and matters set forth therein are true and correct to the best of his knowledge, information and belief.
<q W6t, l W.P.
Stewart Subscribed and sworn to before me, a Notary Public in and for the State and County above named, this 29th day of January, 1979.
4L ()
^
Notary P plic Notary Public, State of Florida at Large, My Commission Expires:
July 25, 1980
e RESPONSE TO NRC REQUEST 10R ADDITIONAL INFOR?tATION QUESTION 1:
Your sutuittal does not adequately identif y the design bases and cri-teria, safety guides and IEEE standards to be im plement ed in the de-sign of this modification to the reactor protection syst2m.
You are requested to address this issue.
RESPONSE
Attached for your review is a copy of the B&W Specifica-tion 08-1004280-01 on the Reactor Coolant Pump Powe r Moni to rs (RCPPM). This specification only addresses the design criteria and bases for the RCP power monitors and excludes any discussion of the interconnecting cable, current and potential transformers and the existing RPS equipment.
This interconnecting cable separation will comply with IEEE Std. 384-1977 and Regulatory Guide 1.75.
The design qualification for the current and potential transformers is discussed in our response to Question #2.
The Reactor Protection System is designed in accordance with IEEE Std. 279, 1968, " Criteria for Nu. lear Power Plant Protective Systems" and IEEE Std. 344, 19 71, "Sc!.smic Qualif icat ions for Class 1 Electrical Equipment for Nuclear Powe r Generating Sta t ions.
Addi-tional discussion concerning the Reactor Protective Systen is contained in Section 7.0 of the CR #3 FSAR and Staf f's Safety Ev.iluatton Report.
To summarize the at tached 1%W s pecif icat ion, the Reactor Coolant Pump Power Monitors are designed on Lt.e following bases:
a.
Criteria for Protection Systems for Nuclear Power Gener it ing Stations, IEEE Std. 279-19/1.
b.
General Guide for Qalifying Class I Electrical Equipment for Nuclear Power Geners: Lion Stations, IEEE Std. 323-1971.
c.
Guide for Seismic Qualification of Class ! Electrical Equipment for Nuclear Power Generating Stations, IEEE 344-1971.
d.
The RCPPM's power is supplied from four separate vital huses.
e.
The RCPPMs are not located inside the containment anc therefore do not have to be ciavironmentally qualifled for the adverse environments associated with accidents inside the cont ainment.
The environmental qualifications of the monitors aie stated in Appendix B of the 1%W specificat ion.
f.
The RCPPMs can be tested with the reactor in operation or shutdown as described in Section 3.1.4 of the 1%W specification, g.
The physical separation and electrical isolation criteria are described in Sections 3.1.16 and 3.1.17 of the imW specification.
QUESTION 2:
The " fall safe" characteristic of the current and potential t rans fo rme rs is not an acceptable alternative to seismic and environmental qtialification of these component s in the reactor safety system.
Therefore, you are requested to reconsider this aspect of your design and report what qualifications these trans formers will have.
RESPONSE
1.
Seismic Qualification Both B&W and Florida Power Corporation (FPC) feel that the Reactor Coolant Pump Monitors (RCPPM) for CR #3 are ef fective protective devices despite the non-seismically qualified Potential Transformers (pts) and Current Transformers (cts) used in this system.
The current B&W design for 177 plants that is being proposed by FPC is consistent with designs being utilized at other operating B&W planta in which seismically quali fied pts and cts were not required. A technical discussion of this B6W and FPC position includes three points :
(1) The cts and pts are pa rt of the process being monitored.
The monitored variable is Reactor Coolant Pump (RCP) power, and the cts and pts are themselves powered by RCP power; therefore, a loss of the monitored variable insures a loss
of output on the monitorir., system.
(2) There is no fa ilure mode of a CT or PT that prohlhtts a loss of RCP signal. cts and pts can fall in any of the fo l l owi ng modes:
CT Failure Ptodes PT Failure Modes Cl Secondary fails open Pi Secondary f alls open C2 Secondary completely P2 Secondary c<unpletely shorts shorts C3 Secondary pa rtially P3 Secondary partially shorts shorts a.
Number of turns a.
Nrmber of turns shorted is such shorted is such that pump power is that pump power is reported at < 70%.
reported at < 70%.
b.
Number of turns b.
Number of turns shorted is such shorted is such that that pump power is pump power is reported at > 70%
reported at >70% but but < 100%.
< 100%.
C4 Secondary shorts to P4 Secondary shorts to the the primary primary PS Primary fails open P6 Primary completely shorts P7 Pcimary partially shorts
a.
Number of turns shorted is stich that pump power is reported at > 110%.
b.
Number of turns shorted is such that pump power is reported at > 100% but
__< 110%.
P8 Fuse open For failure modes Cl, C2, C3a, C4, P1, P2, P3a, P4, PS, P6, P7a and P8 the RCPPet will report the RCP as t ripped to the RPS; however, the RPS (Nuclear Overpower based on RCPPM) will take no action until a second pump is reported tripped.
For failure modes C3b and P3b no RCP trip is reported to the RPS and the RCPPM continues to f unction normally with the exception that this pump power will read lower than normal (70-100%).
If a subsequent loss of pump power were to occur, the RCPPM would register faster than normal.
For failure mode P7b, no RCP trip is reported to t he RPS and the RCPPM continues to function normally with the exception that this pump power will read higher than normal (100-110%).
If a subsequent los s o f pump powe r we re to occur, the RCPPM would register slower than normal, but still within the time assumed in the Accident Analyses.
3.
Even if a hypothetical CT or FT failure mode is assumed, an extremely improbable combinat ion of f a ilure is required to effect the RCPPM input to the RPS.
First, since the RPS for Nuclear Overpower based on RCPPMs has no protection function for the loss of one RCP, at least two Reactor Coolant Pumps must fail simultaneously.
Secondly, two redundant cts or pts in one of the f ailed pumps must also fail simultaneously.
Based on the above discussion, FPC and B & W feel that neismic qualification of the cts and pts is unnecessary for plant safety.
11.
ENVIRONMENTAL QUALIFICATION The Current and Potential Transformers are not located ins id e the containment and will therefore not he sujected to the adverse environmental conditions of the Design Bases Events.
The environmental design criteria for the cts and pts are:
Normal Ambient tempe ra ture 40C nominal 50C ma,:Imtim IOC minimum Pressure Atmosphere llumidity 75 to 100% Ril nominal 100% Ril maximum 0% Ril minimum Chemical content Normal a tmosphere
35S?-20004 (6-76)
BABCOCK & WILCOX NUCLE AR PCWER GENER AfiCN OrvisiCN TECHillCAL DOCUI,1EllT EQUIP.AENT SPECIFICATION 08 2004280 01 Doc.10 - Serial No., Revision No.
fo*
REACTOR COOLANT PUMP POWER F10NITORS PAGE 1
B'.C;P-20005 (6-76)
SABCOCK & WILCOX NUCLEAR POWED CfNttAfiON CIVI$iCN NU"IIE RECOR0 OF REVISION S-4280-01 R E Y. If D.
CHANGE SECT /PA2A.
O E S C 21P il 0 N / Cll A M G E A 'J T110212 A Tl 0 M 01 This revision incorporates approved CI/A Nurber SS-4728-00.
n s,
SA. /n-G'A.
(.NAME)
(TITLE) 0//f/78 (DATEf DATE:
8-16-78 PAGE L1
E'.c;P-20006 (6-76)
BABCOCK & WILCOX Nueste Nutt t AR POWER G[N!#TCN D'VI$pCN TABLE OF C0ilTEilTS/ EFFECTIVE PAGE LIST OS-I m 42S0-01 SECTION TITLE PAGE D 0 0. 10.
1.0 S 0PE 4
08-1004280-00
- 2. 0 APPLICABLE DOCU'ENTS 4
0S-1004280-00 3.0 TECHNICAL REQJIRE?5NTS 4
03-1004230-00 6
08-10042S0-00 7
08-1004280-01 S
08-1004280-00 4.0 EQUIPMENT AND ftATERIAL REQUIREMENTS 9
08-1004280-00 S.0 QUALIFICATION REQUIREMENTS 9
08-1004230-00 10 CS-1004280-00 6.0 QUALITY ASSURANCE REQUIRE?SNTS 10 05-1004280-00 11 OS-1004230-00 12 08-1004280-01
- 7. 0 PACKAGING AND SHIPPING 12 OS-1004280-01 13 0S-1004230-00 APPENDIX A PU'iP POWER.'ONITORS REFERENCES A-1 08-1004280-00 APPENDIX B PERFOR'tANCE REQUIREME.NTS B-1 08-1004280-01 B-2 08-10042S0-01
/JPENDIX C SCOPE OF SUPPLY C-1 08-1004280-00 APPEND 1X D PAINTING REQUIREMENTS D-1 08-1004230-00 FIGURE I RCPPM SCHEME 08-1004280-01 FIGURE 2 SEISMIC FLOOR RESPONSE SPECTRA 08-1004280-00 DATE:
S-16-78
.'\\GE 3
BWNP-20007 (6-76)
BABCOCK & WILCOX NUCLEAR Powit otNERAf ton DmsioN
- yvoie, TEC!UllCAL 000Ut1Eili oS-no42so-oo 1.0 SCOPE 1.1 This specification establishes the design requirements for the reactor coolant pinp power monitor system (RCPP!S) for the Babcock and Wilcox Company (hereinafter referred to as BSW or the Cocpany).
1.2 The RCPPMS is a power nonitor system (PMS) designed to anticipate a loss or reduction of reactor coolant (RC) flow by monitoring reactor coolant pump (RCP) pcwer and detecting abnormal power conditions indicative of an inoperabic pump.
The status of each of four pumps is transmitted by the RCPP!15 to each of four reactor protection system (RPS) channels. Two RCPP!Gs are to be supplied to provide redundant pump status information to each RPS channel.
1.3 This specification identifies the design criteria and functional requirements for the RCPP3S. The design criteria establish the rules by which the elenents shall be designed or selected.
The RCPPMS will become part of the nuclear steam supply syste= (NSSS) of an electrical generation station; therefore, the integrity and reliability of the equipment is of prime importance.
The prinary purpose of the design criteria is to assure a safe and reliable design.
The functional requirements identify the operations and functions to be performed by the RCPPMS.
2.0 APPLICABLE DOCUMENTS The RCPP5G equipment shall meet the requirements of this specification and applicable portions of the documents listed in Appendix A.
3.0 TECHNICAL REOUIREMENTS 3.1 Design Criteria 3.1.1 Applicable Standard The RCPPMS shall meet the requirements of IEEE Standard 279, " Criteria for Protection Systems for Nuclear Power Generating Stations" (Reference 2.1).
3.1.2 Loss of Power Loss of power to a RCPPMS channel shall cause a "Pu=p Not Running" output from that channel.
3.1.3 Equincent Removal Re= oval of a RCPPFG module or subar embly shall cmtse a " Pump Not Running" output from the affected channel unless tuat channel has been bypassed.
DATE:
4-4-78 PAGE 4
B'JP-20007 (6-76)
BABCOCK & WILCOX NUcitAA Powta otstaAboN Division NU"If8 8-4280-00 TECH!!! CAL 0000fjEllT 3.1.4 Testability Manual testing capabilities shall be provided in the RCPPh5 design to accomplish the following:
A.
Preoperational (startup) testing to give maximum assurance that the RCPPh$ and its individual channels will perfom their required and intended functions within specifications.
B.
On-line testing to uncover failures, drift, or loss of calibration.
C.
The requirement to provide en-line test facilities and procedures for the RCPP?G shall be implemented so as to impose the minimum of disturbance to the nomal operation of the plant. Provisions shall not conpromise independence of protection channels.
3.1.5 Environment The RCPPFS shall be designed to the environmental conditi.sns listed in Appendix B.
3.1.6 Serviceability The RCPPSG shall accommodate a reasonable arount of on-line trouble-shooting employing the built-in test and calibration facilities.
As a minimum, a fault shall be locatable to within a major removable element of an instrument channel or protection channel employing the systems built-in test or calibration facilities.
Equipment and subassemblies perfoming identical functions shall be interchangeable between channels.
Interchangeability shall be accomplished with a minimum of adjustments to assure that any affected setpoints will actuate at the correct signal levels.
Modules and equipment shall be clearly labeled according to their function.
All modules which are modified to be functionally unique shall be clearly labeled and bear a different part number.
3.1.7 Reliability The selection of components shall be based not only upon circuit requirements but also upon reliability considerations.
Reliability information, where such data is available on specific components and modules, shall be provided upon request. Reliability considera-tions shall be provided in the proposal.
DATE:
4-4-78 PAGE 5
3WNP-20007 (6-76)
B ABCOCK & NYlLCOX NUCLEAR Powet GEN ER ATCN DIVI $loH NUM 8 t t TEClil!! CAL DOCUMEllT o8- 004230-00 3.1.8 Local Indication The pump power measured by each RCPPFS channel shall be displayed locally in the RCPP55 cabinets.
All bistable devices within the RCPPSS shall have their trip state indicated by visual means.
Local indication shall be provided for power "on", channel trip, channel bypass and channel test.
3.1.9 Remote Indication Contact outputs shall be provided for the Customer's annunciator to provide remote indication whenever a monitor is in a bypassed condition.
3.1.10 Switching Noise The operation of any remote or local switch, which may be a part of the RCPPSS shall not introduce system detected noise or objectionable transients.
3.1.11 Cir uit Breakers The primary side of system power supplies shall be protected by circuit breakers or fuses with open breaker or open fuse indication provided.
3.1.12 Calibration Adjustments Adjustments in the RCPPMS shall be considered as being of two classes; (1) factory (once in a lifetime adjustment) and (2) operator (routine calibration adjustments).
Factory adjustments shall be located where they are not normally accessible to the operator and shall be secured to prevent shifting of calibration.
Any adjustment required for routine calibration shall be located on the equipment front panel. Where precision adjustment is required a vernier dial and/or coarse and fine adjustment shall be provided.
Adjustments for calibration shall not require the removal of equipments from their cabinets or enclosures.
3.1.13 Primary Power The RCPPFS shall be designed for continuous operation when supplied with primary power of 120 VAC t 5% and 60 HZ 15'..
DATE:
4-4-78 PAGE 6
r4NP-20007 (6-76)
BABCOCK & WILCOX Nuum NUCLEAR POWER GENER ADCN Div$oN TECllillCAL DOCUMEllT 8-4 '8 - 1 3.1.14 Drift Drift in the RCPPMS shall not cause the specified accuracy or total error to be exceeded over a 30-day period.
Drift shall be considered as beginning I hour after initial energi:ing of equipment, the equipment being at room ambient just prior to being placed in service.
The I hour warmup allowance shall be considered as a maximum a110wance.
In considering drift, it shall be assumed that all adjustments and calibrations are acconplished immediately following the allowed warmup period.
3.1.15 Seismic Qualification Requirements The RCPP.AG equipment shall be qualified in accordance with IEEE Standard 344-1971, " Seismic Qualification of Class I Electric Equipment for Nuclear Power Generating Stations".
(Reference 2.3, Appendix A)
Refer to Figure 2 for applicable equipment seismic response spectra carves.
3.1.16 Physical Seoaration Two independent power monitor shall be provided for each RCP.
The independent power monitors for a given pump shall be physically separated to minimi:e the likelihood of a single event impairing the intended function of both monitors.
Each monitor shall provide contact outputs to four independent RPS channels.
The contact outputs to each channel from a given monitor shall be physically separated.
3.1.17 Electrical Isolation The RCPPMS shall be designed such that electrical faults occuring on signal lines feeding the RCPPMS or electrical faults within the RCPPMS circuitry are not propagated into any RPS channel.
An electrical fault is defined as the inadvertent short circuiting, grounding or opening of an electrical circuit or the connection of an electrical circuit to a foreign source of electrical energy.
The foreign source voltage is 480 VAC RMS with no current limiting.
(01)
DATE:
8-16-78 PAGE 7
BWNP-20007 (6-76)
BABCOCK & WILCOX uuusen suctsas rowra c(NERAboN OmstoN Q3.lQQ423Q..QQ TECWilCAl. DOCUf.lEllT Further, the RCPPFS shall be designed such that two or more RPS channels cannot interact or be cross-coupled due to electrical faults occuring on signal lines feeding the RCPPFS, signal lines leaving the RCPPSS, signal lines leaving the RCPPFS or electrical faults within the RCPPMS circuitry.
Sufficient isolation shall be provided such that the application of a foreign source voltage of 480 VAC RMS across the contacts outputting to a givcn RPS channel will not result in the propagation of that fanit to any other RPS channel.
3.2 Functional Reouirenents 3.2.1 The mission of the RCPPNS is to riport to the RPS the running /not running status of each RCP. The RCPP55 shall detenr.ine the status of each pump by monitoring the electrical pcwer to the pump and providing a digital signal output whenever the monitored power is outside a selected allowable band. The RCPP35 shall report a
" Pump Not Running" status for the following conditions:
A)
Total loss of electrical power to the monitored pump motor.
B)
Locked rotor.
C)
Loss of motor load (broken shaft or dropped pump impeller).
3.2.2 Figure 1 shows the overall RCP power monitoring scheme for one pump monitor.
The items enclosed within the dashed line are in the RCPPMS scope.
The carrent and potential transformers providing input to *:.e ni' OMS will be supplied by others.
Interface inforr.cion for these trrasformers is in Appendix B.
3.2.3 Two indepe-power monitors shall be provided for each RCP.
A total of
.ht monitors are required to provide two monitors for each of four pumps. The two independent monitors for a given pump shall be housed in separate cabinets.
It is permissible to house one set of monitors (one for each pump) in one cabinet and the independent set of monitors in a second cabinet.
3.2.4 Each monitor shall provide four isolated contact outputs.
Each contact output shall be dedicated to one of four separate RPS channels.
An open contact shall correspond to a " pump not running" condition.
The contact outputs from two independent monitors will be combined external to the RCPPNS to provide a one-out-of-two input to each RPS channel.
3.2.5 The design of the RCPPNS shall be such that the RPS will not receive a " Pump Not Ruaning" signal when changing the power source to the RCP bus.
The nominal time required for this transfer is 0.100 seconds.
DATE:
4-4-78 PAGE 8
3'.sP-20007 (6-76)
BABCOCK & WILCOX Numin NUCLE 48 POWER C(NER AfsoN Divi $loN TEClll!ICAL 00CtHJE!!T 8-428 -
3.2.6 The accuracy and time delay requirements for the RCPPMS are given in Appendix B.
3.2.7 The pump nonitor output contacts shall not lock in for a " Pump Not Running" condition.
The contacts shall reset instantaneously upon return of pump power to the allowable band.
3.2.8 The required range of adjustment on the RCPPh5 trip setpoints is given in Appendix B.
4.0 EQUIPMENT AND htATERIAL REQUIREMENTS 4.1 Vendors Scope of Supply ihe items of hardware that are to be supplied under the terms of this specification are listed in Appendix C.
4.2 Eauipnent Cabinets The RCPPMS cabinets shall be supplied completely wired and assembled.
The Vendor shall be responsible for the internal layout designs of the cabinets and shall comply with the physical separation and electrical isolation requirements of Paragraphs 3.1.16 and %.1.17 The cabinets shall be supplied with access doors provided v :S key locking door handles.
4.3 External Wiring The RCPPh5 cabinets shall be provided with top access for all external wiring.
External cable connections to the cabinets shall be via terminal boards located within the cabinets near the cable entrance.
4.4 Painting After fabrication, the RCPPMS cabinets interior and exterior surfaces, including doors and access covers shall be cleaned, pri=ed and painted in accordance with the requirements of Appendix D.
4.5 Identification The RCPPMS cabinets shall be provided with permanently affixed cetal identification tags.
These tags shall include at least the following:
A.
BGW contract number.
B.
E 5W equipment identification number.
C.
Ultimate Customer identification number.
DATE:
4-4-78 PAGE 9
3WNP-20007 (6-76)
BABCOCK & NVILCCDC NucttAt PowtR GENER ADCN Drvi$10N NUMBER TECHf!! CAL 0000f.1Elli o8-to04290-00 5.0 QUALIFICATION REQUIREMENTS 5;
Oualification Methodology Tiw equipment specified herein shall be qualified to provide assurance that installed equipment will meet or excesd the perforcance requirements of this specification.
Qualification shall be in compliance with the references listed in Appendix A.
Qualification shall be accomplished by type test or a combination of t>7e test and analysis. Type testing is the preferred method and requires that each mode'. A;d type of equipment offered be subject to the environments and cierating conditions corresponding to the service conditions for each application specified herein. Analysis may be used to supplement type test data by reasonable engineering extrapolation to show that the available data conservatively envelopes the performance requirements of this specification for those applications ni ' tested.
5.1.1 Traceability Traceabilit-/ shall be demonstrated by appropriate documentation for the fo11 swing:
5.1.2 Design Traceability The design of the test unit (s) shall be traceable to the units to be shipped.
5.1.3 Specification Traceability Test unit (s) shall be traceable to the specific application being gr _lified in terms of model number, type and range.
Test unit (s) environments, operating conditions and test levels shall be traceable to service conditions of this specification.
The testing acceptance criteria shall be traceable to the perfor=ance requirements of this specification.
6.0 OUALITY ASSURANCE REQUIREMENTS The Vendor shall maintain a QA program in accordance with the applicable sections of the B5W Specification for Nuclear Quality Program Requirements, Reference 1.1.
The iespections, tests, and documentation necessary for the Vendor to meet the requirements of the QA program and the requirements of this specification are defined in this section.
The documentation requirements are also listed on the quality requirements matrix (QRF0, (Reference 1.2).
DATE:
4-4-78 PAGE 10
B' rip-20007 (6-76)
BABCOCK & WILCOX NUCLEAR Powf a GENERAfloN Division uu ::
TECllillCAL 00001,1EllT 3-1 42s0-00 6.1 Inspections Requirements for inspection by the Vendor and the Company are specified in Reference 1.1.
6.2 Testing of Production Units Prior to shipment, the Vendor shall arrange for the Company and their Customer to witness an operational performanc; test of the completed system.
The performance test shall demonstrate to the Company that all requirements of this specification have been met when the system is calibrated and aligned in accordance with the calibration and alignment procedures contained in the Vendor instruction manuals for the system.
A performance test specification shall be prepsred by the Vendor subj ect to B5W approval.
The test specifi cation shall include test procedures and acceptance criteria.
The Vendor shall provide documentary evidence of the ability of the system to meet those requirements which cannot reasonably be demonstrated at the Vendor facility.
6.3 Documentation 6.3.1 Qualification Report For the first-of-a-kind (FOAK) contract to meet this specification certified reports with procedures shall be submitted by the Vendor for B5W approval. The report shall include the type test data to show that all the qualification requirements of this specification have been met.
The report shall also include documentation to demonstrate traceability as required by Section 5.1.1 above.
5.3.2 Procedures The performance test specificatio submitted for approval prior to use. required by Section 6.2 shall be 6.3.3 Certificates of Conformance (COC)
A C0C certify' ing that the qualification requirements of Section 5.0 have bee st must be submitted prior to release for shipment.
6.3.4 Data The results of the performance test required by Section 6.2 shall be suFaitted as part of the QA data package.
DATE:
4-4-78 PAGE 11
BWNP-20007 (6-76)
BABCOCK & WILCOX NUCLEAR Powta G8NER ATioN DIVl$loN y3,,,
TECll!!! CAL 000U'JElli os 004280-0i 6.3.5 Drawings Design drawings shall be submitted for approval.
The design drawing (01) package shall consist of the items listed below.
Items A, B, and C require approval prior to release for manufacture.
Items D, E, F and G regttire approval prior to system performance test.
A.
Cabinet Mounting Details B.
Cabinet Outline C.
External Connections D.
Cabinet Internal Assembly E.
Front Panel Layout and Marking F.
Niring Diagrams G.
Schematics 6.3.6 Instruction Books The Vendor shall submit instruction books for approval prior to shipment of equipment.
The instruction books shall contain sufficient information to enable the ultimate Customer to properly install, operate, and maintain the equipment.
The instruction books shall also contain a detailed parts list, a list of recommended spare parts and Customer guidance on replacement of qualified parts.
Quantities of instruction manuals to be submitted shall be as specified in the purchase order.
6.3.7 Packaging and Shi_opir; Instructions Documentation, including packaging standards, shipping instructions, and storage instructions, shall be submitted for approval prior to us e.
7.0 PACKAGING AND SHIPPING 7.1 The cabinets shall be packaged for shipment with all equipment that is to be cabinet-mounted by the Vendor installed in the cabinet except that the delicate devices which may be so designated shall be removed from the cabinets, packaged and shipped separately.
The Vendor shall provide any packing of the cabinets and associated system equipment and take any other measures necessary to prevent damage during shipment. All packages, crates, or boxes, shall be plainly marked for identification of contents.
7.2 Cabinets or equipment requiring field storage prior to erection most be packaged in such a manner so as to prevent deterioration and damage.
Instructions concerning storage requirements must be so labeled clearly on the container or package. When packaged desiccants (to be non-chloride type) are to be placed inside the equipment package, the following marking shall be prominently displayed the equipment:
" CAUTION - RE?OVE DESICCANT PACKAGES BEFORE USE."
DATE.
8-16-78 PAGE 12
3W'iP-20007 (6-76)
BABCOCK & WILCOX NucttAt Powta CtNta AricN olvisioN Nues te TEC!!!!! CAL 00CUl.1EllT 8-i 42s0-00 All equipment packed with desiccant shall also have a coisture indicator included in the package with the desiccent package.
7.3 All components requiring indoor storage prior to erection shall be shipped in closed, weathertight carriers where the carrier is defined as a mode of transportation, not the packaging or crate.
7.4 Cabinets or equipmant tl.at are too cumbersome or heavy to be easily handled by personnel shall be prepared for shipnent so that mechanical handling equipment cay be used.
Fork lift pallets and crane slings, if used, cust be readily accessible while the cabinets or equipment are on the carrier.
7.5 All parts exceeding 200 pound gross weight shall be prepared for shipment so that slings for handling by the crane cay be readily attached while the parts are on the carrier.
Boxed parts, where it is unsafe to attach slings to the box, shall be packed with slings attached to the parts, the slings to project through the box or crate so that attachments to the hosting equipment can be readily made.
7.6 All paint applied by the Vendor shall be thoroughly dry before packaging or shipping the equipment to minimize damage to the paint.
In addition, the Vendor shall take whatever ceasures he considers necessary to assure that the paint finish will not be damaged as a result of packaging, crating, handling and transpor-tation hazards encountered.
DATE:
4 4_78 PAGE 13
B'aP-20007 (6-76)
BABCOCK & WILCOX wuut et NUCLgAt POWER GEN ERAtlCN OlVI$loN TEClittlCAl. DOCUi.!EilT 03-1004:30-00 REACTOR COOLANT PUMP PCNER !ONITORS REFERENCES 1.0 BSW DOCUMENTS 1.1 Specification 09-1212-01, " Quality Assurance Program Requirenents for Nuclear Equipment".
1.2 Quality Requirenents Matrix (QRM) for Reactor Coolant Pump Power Monitors, BSN Drawing ?hnber 48-1003376-01.
2.0 INDUSTRY STANDARDS 2.1 IEEE Standard Criteria for Protection Systems for Nuc1 car Power Generating Stations, IEEE Std. ~79-1971.
- 2. 2 General Guide for Qualifying Class I Electrical Equipment for Nuclear Power Generation Stations, IEEE Std. 323-1971.
- 2. 3 Guide for Seist.iic Qualification of Class 1 Electrical Equipment for Nuclear Power Generating Stations, IEEE 344-1971.
DATE:
4-4-78 Appendix A, Page A-1
3'a7iP-20007 (6-76)
BABCOCK & WILCOX Nu. set NUCLEAR Powlt GEN ER ATioN DIVI 5 ION TECHillCAL DOCUI1Elli Os-10042s0-01 PERFORMANCE REQUIREMENTS 1.0 ENVIRON >tENTAL CONDITIONS 1.1 Ambient Temperature 40F minimum 75F nominal 110F maximum 1.2 Anbient Pressure Atmospheric 1.3 Relative Humidity 10'. minimum 50% normal 50% maximum 1.4 Radiation
Background
2.0 INTERFACE REQUIREMENTS 2.1 RCPPMS Inputs Potential Transformer Ratio 7200/120 (01)
Potential Transformer Output 60HZ, 120VAC Current Transformer Ratio 1200/5 (01)
Current Transfomer Output 0-5 Amps 2.2 RCPPMS Outputs The minimum contact rating of the outputs to the RP5 shall be 20 ma @ 125 VDC, resistive load.
The minimum contact rating of the outputs to the plant annunciator shall be 20 ma 9 125 VDC, resistive load.
(01) 3.0 CALIBRATION 3.1 Instrument Transformer Outputs Potential Transformers 0-120 VAC Current Transformers 0-5 AMPS 3.2 h'att Transducer Calibration The watt transducer full scale output shall correspond to potential transfomer inputs of 120 VAC and current transformer inputs of 5 amps.
DATE.
8-16-78 Appendix B, Page B-1
BWNP-20007 (6-76)
BABCOCK & NVILCCU(
Nuo t t a NUcttAt Powlt G(Ntt AlloN Division TECliillCAL 0000l.1ENT 8-tood:So-01 4.0 RANGE OF ADJUSTMENT Underpower Setpoint 0 to 60% of Natt Transducer Full Scale Output Overpower Setpoint 40% to 100% of Watt Transducer (01)
Full Scale Output Deleted.
(01) 5.0 ACCURACY REQUIRE!ENTS 5.1 Overall Accuracy The overall accuracy of the RCP.?MS shall be such that the RCPPMS bistable changes state when the input to the RCPPMS is at the under-power setpoint li and when the input to the RCPPMS is at the overpower setpoint 11'..
This accuracy requirement shall be met for the range of environmental conditions in 1.0 above and the range of setpoints in 4.0 above.
5.2 Time Delay The maximum permissible delay between the time when the input to the RCPPMS reaches the overpower or underpower setpoint value and the time when the contacts to the RPS open is 240 milliseconds.
This requirement shall be met for the range of environmental conditions in 1.0 above and the range of setpoints in 4.0 above.
5.3 Seismic Accuracy and Time Delay The accuracy and time delay requirements of 5.1 and 5.2 above shall be met during and after the RCPPMS cabinets are subjected to the seismic input corresponding to the floor response spectra of Figure 2.
DATE.
8-16-78 Appendix B, Page B-2
B',iNP-20007 (6-76)
BABCOCK & WILCOX Nuu s ta NUCLEAR Pow t A GENER AflCN 0;Vi$loN 8-423 -
TECliillCAL D000l1EllT SCOPE OF SUPPLY 1.0 HARDWARE 1.1 RCPP.'G Cabinets 1.2 RCPP'S cabinet mounted equipment necessary to fulfill the requirements of this specification.
2.0 DOCUMENTATION All <iocuments, drawings and instniction books as required by this specification and the QRM.
3.0 EQUIP 5ENT NOT INCLUDED 3.1 Interconnecting cable.
3.2 Current and potential transfomers.
3.3 RPS equipment.
DATE:
4-4-78 Appendix C, Page C-1
%7;P-20007 (6-76)
BABCOCK & WILCOX HvCLE AR Pow Et GENEk ATON 0:Visio N wu= R e t TECilillCAL DOCUME!!T 08-1004230-00 PAINTING REOUIRE!5NTS The RCPP?tS cabinets shall be painted in accordance with the following:
Primer paint for exposed surfaces shall be a red oxide or zine chromate
- pigment, rust inhibitive netal priner paint recer. ended by the paint manufacturer for service intended and for application to metals prepared for painting by wire brush.
Priner paint with the paint nanufacturer's reconmendations.shall be aplied in accordance ANSI 61 light gray baked synthetic enanel.
Finish paint shall be of DATE:
4-4-78 Appendix D, Page D-1
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