ML17309A334
| ML17309A334 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 03/30/1984 |
| From: | Kober R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17255A748 | List: |
| References | |
| NUDOCS 8404100406 | |
| Download: ML17309A334 (107) | |
Text
REGULATORY INFORMATION DISTRIBUTION S ~."Efd (RIDS)
A'CCESSION NBRe8004100006 POC ~ DATE>> 84/03/30 NOTARIZED; NO . DOCKET BYNAME FACIL:50 240 Robert Emmet Ginna Nuclear Planti Unit 1E Rochester G 05000244 AUTH AUTHOR AFFILIATION KOBEReR ~ 5 ~ Rochester Gas 5 Electric Corp.
REC IP ~ NAME RECIPIENT AFFILIATION CRUTCHFIELDg D ~ Operating Reactors Branch 5
SUBJECT:
Forwards addi documentation for any unresolved issues noted in Franklin Research Ctr Technical Evaluation .Rept TER-C5257"054 re environ qualification of electrical equipment. Pro rietary version withheld.
DISTRIBUTION CODE: A 8S COPIES RECEI YED:LTR.JENCL TITLE: OR/Licensing uumittal: Equipment Qualification NOTES:NRR/DL/SEP 1cy. 05000244 RECIPIENT COPIES REC IP IENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL" NRR ORBS BC 12 1 0 DICK i G ~7 1 INTERNAL: ELD/HOSE IE .FILE NRR/DE/EQB (o
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ROCHESTER GAS AND ELECTRIC CORPORATION D 89 EAST AVENUE, ROCHESTER, N.K 14649-0001 ROGER W. KOBER VICE PRESIDENT TELEPHONE ELECTRIC & STEAM PIIDDVCTION AREA CODE TIE 546-2700 March 30, 1984 Director of Nuclear Reactor Regulation Attention: Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch No. 5 U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Environmental Qualification of Electrical Equipment R. E. Ginna Nuclear Power Plant Docket. No. 50-244
Dear Mr. Crutchfield:
The purpose of this submittal is to provide additional documentation for, any unresolved issues noted in the FRC Technical Evaluation Report, TER-C5257-454. For convenience, we will also summarize the content and provide the submittal dates of items considered resolved in other RG&E correspondence since the December 13, 1982 "Safety Evaluation Report for Environmental Qualification of Safety-Related Electrical Equipment", which transmitted the FRC TER.
Enclosure 1 provides the necessary information. Additional References 77-84, as well as two updated Documentation Reference sheets are also attached. Please note that. Reference 78 is proprietary in nature. A letter from Kerite requesting that. this information be maintained confidential is enclosed with Reference
- 78. Thus, this information should not be placed into the Public Document Room. Based on this submittal, RG&E considers that all environmental qualification issues resultant from the FRC review are now resolved, pending final installation of equipment scheduled for the 1984 refueling outage and submittal of related qualification documentation.
e y truly yours, er ul/
W. Kober Enclosures IIIP] (
8404100406 840330 y5I6 PDR *DOCK 05000244 P ', PDR pg)5
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Reference 82 Post Accident Sampling System NUREG-0737 requires that the plant have the ability to draw a reactor coolant sample. This will be performed through a sampling line already in existence at Ginna. The only modification inside containment to perform this sample is replacement of the solenoid for valve 955 with a qualified solenoid. This is being performed in conjunction with the replacement of solenoid valves as needed for items l, 2, 4, 5, 6, 8 and 9. The qualification report will be added as Reference 82 following installation of the solenoid.
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Enclosure:
Status of Environmental Qualification of Electrical Equipment per TER-C5257-454 Item Numbers 1, 2, 4, 5, 6, 8, 9 Solenoid valves (various).
As provided in RGsE's February 1, 1983 letter, these solenoid valves will be installed and operable following the Spring 1984 refueling outages. The test reports for the ASCO and VALCOR solenoid valves will be available for review in RG&E's files. A summary of the test results will be submitted to the NRC following receipt of all documentation by RG&E.
- 2. Item Number 10 Solenoid valve for the pressurizer PORV.
The applicable qualification document was previously submitted as Reference 73, "QR52600-5940-2". As noted in Attachment 2 of our February 1, 1983 submittal, a similarity report from VALCOR was being provided to RG&E, for transmittal to the NRC. This letter is included in this submittal as Reference 77, "Similarity Qualification Test Report SKA 11419, Solenoid Valves for Rochester Gas and Electric Corp."
Item Numbers 13, 14 Limitorque valve operators for valves 826 A-D, 896 A and B, and 825 A and B.
As noted in our September 4, 1981 submittal, "aging" is addressed in our Reference 53, which is Limitorque Report B0003.
It is important to note that in our we stated that, these valves are not October 31, 1980 submittal, exposed to a DBE environment prior to the time-at which they complete their safety function.
Therefore, these valves actually should be categorized as being installed in a "mild environment."
4 ~ Item Numbers 16, 18 Limitorque operators for valves 850 A, Bg 857 Ag Bg C 856 860 A Dg 704 A~ B 852 AgB ~
As noted in RG&E's previous submittal of September 4, 1981, the issue of "aging" is addressed in our Limitorque Qualifi-cation Report B0003.
- 5. Item Number 27 Hydrogen Recombiner Blower Motor.
Two items of concern were raised in the FRC TER; qualified life and splice material evaluation.
As noted in the qualification document WCAP 7410-L, the motor was qualified for 7 years continuous duty at 150'C.
Since the motor is not generally used except for testing, and the containment ambient is about 50'C, a 40 year life is certainly assured.
During the 1982 refueling outage, RG&E replaced the motor-to-lead splice insulation with qualified Raychem sleeves (designated as Category I.a in the FRC TER) .
Item Numbers 29, 30 Cooling fans for motors for RHR, Charging, SI, and CS pumps.
As noted in RG&E's reference 69, Westinghouse Report 71-1C2-RADMC-Rl entitled "Effects of Radiation on Insulating Materials Used in Westinghouse Medium Motors", all typical materials and combinations used in the motors, including connections and greases, have been tested by Westinghouse.
The only adverse environment which might be experienced by these motors is radiation, which has been conservatively estimated at 2.8 x 10 rads. As noted in the test results, only Polyester and Teflon were at all susceptible to degradation at this level of radiation. These materials are not used in our motors. Thus, RG&E has concluded that the motors are qualified for their intended services.
It is also noted in the report that. these motors have an expected operating life of 20 years. Since the motors are used intermittently, and are not operated at their maximum rating at all times, a 40-year life can be expected. Further, all fans and motors are lubricated and inspected on a periodic (roughly one year) basis in accordance with the Ginna Station preventive maintenance program. These are detailed primarily in procedures A-1011, PM-2, PM-3, and M-45.2 If any signs of degradation are apparent, major maintenance such as insulation replacement is scheduled and performed in accordance with these maintenance procedures.
Thus, the RG&E program ensures that failure due to aging is minimized.
Equipment Item No. 33 Terminal blocks.
As noted in RG&E ' February 1, 1983 submittal, these terminal blocks were replaced with Raychem sleeves during the Spring 1982 refueling outage.
Equipment Item Numbers 34, 35 Kerite Cable in Containment.
As noted in our February 1, 1983 submittal, RG&E considers the full range of Kerite power and control cable used at Ginna to be properly environmentally qualified. However, we have received another report from Kerite documenting environ-mental qualification for cable used at Ginna. This proprietary report, is attached as Reference 78. The confidential attachments are not being submitted; however, they are available for review at RG&E.
As noted in the cover letter to this reference the testing was performed for a No. 16 AWG conductor, rather than'o. 10 Based on a comparison of the insulation and jacket.
thicknesses, it is considered that the differences are AWG.
insignificant. Thus, cable installed at it Ginna can be concluded that, the Kerite is properly environmentally qualified.
Equipment Item Numbers 37, 38 Coleman cable inside and outside containment.
In RG&E's letter of September 7, 1981 a response was provided relative to the radiation qualification of the Coleman cable (i.e., DOR Guidelines are met).
In RG&E's letter of February 1, 1983, Reference 76 was provided to show that the materials of construction of the cable outside containment could meet and exceed the required post-accident dose.
RG&E thus considers these items to be resolved.
Equipment Item Numbers 39, 40 Rome and General Cable Outside Containment.
Reference 76 was provided as an attachment. to our February 1, 1983 letter. This reference provided the necessary radiation qualification information for the material of construction of this cable; thus, RGGE considers these items resolved.
Equipment Item Numbers 41-47, 49 Transmitters.
Allof these transmitters have been replaced with Foxboro NE Series transmitters. See the discussion for item 3 of Attachment 1 to our February 1, 1983 letter.
Equipment, Item Number 48. BAST level transmitters.
The BAST level transmitters are located in the auxiliary building, and provide signals to automatically switch the suction source of the Safety Injection Pumps from the BAST to the RWST. This function is completed before there would be any sump recirculation. Thus, these transmitters are required to perform a safety function in a "mild" environment.
Equipment, Item No. 50 Reactor Coolant Temperature RTD's.
As noted in our February 1, 1983 submittal, RG6E does not at, this time consider the TC RTD's to be required for operation in a harsh environment. RME will have installed qualified Conax RTD's in the hot legs by the end of the 1984 refueling outage. These RTD's are relied upon for input to the saturation meter. The cold leg temperature indication is used as
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back-up information t'o help determine natural circulation, and as such it is not considered to require full environmental qualification. A summary of the qualification test, report for Conax RTD's is included as Reference 79. The entire report is on file at the RG&E offices, and can be reviewed if desired.
- 14. Item Number 55 Reactor Containment Fan Cooler Motors.
In our February 1, 1983 submittal, RG&E discussed most of the designated open items. Additional information is as follows:
a) Motor Inspection, Including Bearings:
During the Spring 1983 refueling outage, RG&E removed and inspected the fan cooler motor and bearings. These were found to be in excellent condition. Although not.
necessary, the bearings were replaced. The original bearings are currently available at RG&E for inspection,
, if desired. The motor, windings, and splices were also in excellent condition, with no abnormal signs of degradation.
b) Changeout of Grease:
Chevron NRRG grease is now being used in these motors.
A copy of the Chevron bulletin, and applicable pages of Ginna procedure A-1011 are included with this report as RG&E Reference 80.
c) Radiation Qualification:
The radiation qualification testing used to qualify the motors used industry standard gamma techniques. As noted in Regulatory Guide 1.89,... "NUREG/CR-2089 concluded that standard gamma simulators can adequately duplicate damage from both ambient and accident radiation environments"... Thus, this issue is considered resolved.
- 15. Equipment Item Numbers 56, 57 Switchgear.
An explanation was provided in RG&E's February 1, 1983 submittal.
- 16. Equipment, Item Number 62-Sump "B" Level Detectors.
These detectors have been replaced with qualified Trans-america DeLaval (GEM) units Part No. LS57761. Excerpts of the qualification documentation is provided as- Reference 81.
The entire set of qualification reports "Nuclear Qualification Test Program on a Liquid Level Transmitter and Receiver" Report Nos. 45700-1 and 45700-2 are on file at, RG&E, and can be reviewed if desired. The first report documents qualifi-cation for radiation, aging, seismic, and abnormal conditions.
The second report documents the LOCA/SLB accident environmental testing. Note that the qualification reports are for Part No. XM-54854.
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A letter documenting that the tested units are similar to the installed units is also being transmitted as part of Ref. 81. Finally, RGEE has, as required in the test conclusions, provided qualified interconnect cable for equipment interface.
A summary of documentation relative to the qualification of the Boston Xnsulated wire cable used is also provided as part of Reference 81. Test Report 915, "Flame and Radiation Resistant Cables for Nuclear Power Plants" 11/80, is on file at RGGE.
- 17. Equipment Item Number 63 Hydrogen Recombiner.
As noted in the Franklin TER, "pending the successful reso-lution of the pressure switches outstanding item, this equipment is considered qualified". RG6E has decided to replace the Barton pressure instrumentation with fully qualified Foxboro NE-Series transmitters (see item 11 above) during the 1984 refueling outage.
- 18. Equipment Item Number 64 Namco limit switch.
As noted in RG&E February 1, 1983 submittal, the model number of the installed switches is EA180-11302, identical to those in the test report. This item is considered resolved.
~ 19. Equipment Xtem Number 65 LVDT for pressurizer safety valves.
This item was discussed in RGEE's February 1, 1983 submittal.
The installed units are 500 XS-ZTR. As noted in the Franklin TER, "...when model No. 500XS-ZTR is installed qualified to NUREG-0588 Category I..." it will be
- 20. Equipment Xtem Number 66 Valcor SOV's for the reactor vessel head vent.
As discussed in our February 1, 1983 submittal, it has been confirmed that, the model number of the installed valves is V52600-6042. This is included in the listing of vales qualified by test report QR-52600-5940-2, Reference 73.
Thus, this item is considered fully qualified.
- 21. Equipment Xtem No. 67 Cont. Pressure Transmitters.
RGGE has replaced these transmitters with fully qualified Foxboro NE-Series transmitters (see item 11 above).
In addition to the explanation of the items discussed in the Franklin TER, RG&E will address additional equipment installed, either as a result of TMI issues, or for other reasons.
z~. Transmitters In addition to equipment items 41, 42, 43, 44, 45, 46, 47, 49, 63, and 67, which are Foxboro NE-Series, transmitters, RG&E has also replaced the transmitters which monitor other parameters, even though not all are required
to perform a safety function in a harsh environment. These additional transmitters are:
- a. RC Wide Range Pressure (0-3000 psig) PT-420, PT-420A Foxboro Model Number N-E11GH
- b. Auxiliary Feedwater Discharge Pressure (0-2000 psig)
PT-2019, 2029, 2030 Foxboro Model Number N-E11GM [TMI II.E.1.2]
- e. Condensate Storage Tank Level (0-24') LT-2022, LT-2022A Foxboro Model Number N-E13DM
- f. AFW Flow (0-300" WC) FT-2001, 2002, 2013, 2014 Foxboro Model Number N-E13DM [TMI II.E.1.2]
- g. AFW Flow (0 120 WC) FT 20006'007'009 2015 Foxboro Model Number N-E13DM [TMI II.E.1.2]
When RG&E's October 31, 1980 report is fully updated, the installation of these transmitters will be noted.
be noted that the Franklin TER suggests CVCS flow be added It should to the listing of environmentally qualified parameters.
RG&E does not consider the CVCS flow instruments to be in a harsh environment (it would be used for normal shutdown only, since SI is used for accidents), and pressurizer level is the parameter which would be used as the prime indication of RCS inventory control. Thus, CVCS flow has not been added to RG6E s list of environmentally qualified instrumentation.
- 24. Post-Accident, Sampling System, TMI Item II.B.3.
The only portion of the PASS required to be environmentally qualified is the equipment. used to draw a reactor coolant sample. This consists of replacement of the solenoid for SOV 955. This solenoid is being installed in conjunction with those being supplied as items 1, 2, 4, 5, 6, 8 and 9.
The schedule for installation and documentation is provided in paragraph 1 of this enclosure.
- 25. Hydrogen Monitors. TMI Item II.F.1.6. These monitors are provided by COMSIP, Inc. Pertinent, excerpts, provided as Reference 83, are enclosed. The entire proprietary report is on file at, RG&E. A discussion of the retest of the sample pump is also provided in the excerpts from EAST Project 1035-8, included as part of Reference 83.
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Lubricants. The lubricants used'or motors at Ginna Station are primarily Mobil oils, such as DTE 25, 26, and Mobilux EP.1 and EP.2. As stated in enclosed Reference 84, these lubricants have a radiation resistance in excess of 3x10 rads. Since )he greatest dose expected in these applications is about 3x10 rads (RHR pumps), significant margin is apparent.
- 27. Regulatory Guide 1.97 Guidance. A comparison of RG1.97 to present RG6E instrumentation was provided in a letter from John E. Maier to Dennis Crutchfield dated January 31, 1984.
RGaE Reference 77 VAlCOR VAI.COB ENGINEERING CORPORATlON 2 LAWRENCE ROAD, SPRINGPIELD, NEW JERSEY 07061, USA. ~ (201) 467.8400 TWX 710-996.6976 ~ CABLE: VALCOR Similarity Qualification Test Report SKA 11419 Solenoid Valves For Rochester Gas t'1 Electric Corp.
INTRODUCTION The valves supplied to Rochester Gas 5 Electric Corp. on P.O. 836725-1500-08 are qualified on the basis of similarity to previously qualified valves.
DISCUSSION Valcor Qualification Report QR52600-5940-2 (Reference 1) documents the procedures and tests conducted to qualify Valcor Series V526 solenoid valves to IEEE Standard 323-1974, based on the following conditions, without-degradation of performance.
- 1. Normal environment of 120 F (maximum) for 40 years (minimum)
- 2. Experience a 2xl0 8 RAD intergrated radiation dose.
- 3. Operate a minimum of 45,000 cycles, each cycle not exceeding one half hour duration.
- 4. Sustain a 4.5g minimum seismic event.
5: Experience two LOCA onsets of 346 F and 113 psig and sustain a post LOCA environment for 6.2 years minimum at 130 F.
The valves supplied to Rochester Gas 5 Electric Corp. are qualified'n the basis of similarity as outlined below:
The following valve is structurally similar to valve V57300-5220-1 which was seismically qualified and reported in MR57300-5220-1-2, (Reference 2) except that the solenoid assembly construction is similar to valve V52600-6042-1 noted in Table I of QR52600-5940-2.
V573-5242-1 All electrical components housed within the solenoid assembly are identical to the hardware qualified. Changes such as the elimination of the zener, the rectifier or the position indication switches do not effect qualification.
Sheet 1 of 3
l P ~u SKA 11419 Sheet 2 of 3 VALCOR ENGINEERING CORP.
DISCUSSION (continued)
The materials used in the pressure boundary assemblies of the subject valves and those used in the qualification valves are in accordance with the ASME Boiler and Pressure Vessel Code,Section III. Table I shows the similarities of materials used in these valves and qualification test valves.
The other non-pressure boundary materials in these valves and qualification test valves are also similar.
CONCLUSION Qualification is extended to the subject valves because .of their similarities of design, material, construction and load requirements to the previously qualified valves in Reference,l.
REFERENCES
- 1. QR52600-5940-2, Qualification Test Report on SNUPPS Solenoid Valves.
- 2. MR57300-5220-1-2, Seismic Qualification Test Report on Solenoid Valve P/N V57300-5220-1.
.H Boroson Assistant Chief Project Engineer
ROCHESTER GAS 4 ELECTRIC CORP.
VALVE NOMINAL (3) SEAL BODY (1) BONNET (2) FLOW RATING MODEL NO. SIZE (IN) TYPE .MATERIAL MATERIAL MATERIAL CAPACITY (CV) CLASS V573-5242-1 Vespel C B 5.0 150 IEEE - 323-1974 QUALIFICATION TEST VALVE V52600-5291-2 3/8 EPDM 0.8 150 LIFE CYCLE TEST VALVES V52600-5291-2 3/8 EPDM 0.8 150 V52600-5940-2 1 Carbon 2.0 600 SEISMIC TEST VALVES.
V52600-6042-1 1 G Stellite 6B A 2.0 2500 V57300-5220>>1 1 H Vespel 'A 4.0 150 (1) Body MTL:
A - ASME SA240, Type 316 C - ASME SA515, Grade 70 D - ASME SA182, Type 316 (2) Bonnet mL:
B ASME SA-479, Type 316 (3) E Direct Operating Poppet F - Direct Operating Shear Seal G - Pilot Assist Poppet H Direct Operating Balanced Poppet SKA 11419 Sheet 3 of 3
VAlC8iP DTF 001 VALCOR ENGINEERING CORP DA TE 3/1 8/83 2 Lawrence Road, TWX BIO Springfield, tt6 Sttt Mtlt. VAlCOt NJ 07081 ORIGINATOR DATA TRANSMITTAL FORM TO
"
Rochester Gas 6 Electric Corp. PROJECT:
8 East Avenue hester N. Y. 1464 CONT. NO..N-EG-32516 EWR S/O.
G. Wrobel 2292 REPLY BY:
ITEM COPIES NO. DOC. NUMBER REV DESCRIPTION REF P T 01 SKA 11419 IEEE Report REMARKS:
RGGE Reference 79 IPS-798 DESIGN QUALIFICATION TEST REPORT FOR CONAX RTD ASSEMBLIES FOR CLASS lE APPLICATIONS IN NUCLEAR POWER PLANTS L'L7EPL7EAIIL7k'300 WALOEN AVE., BUFFALO, N.Y. I4225 ~ 7IB 6844500 ~ TELEX 9I 275 ~ CABLE CONAXCO
CONAX CORPORATION 2~00 Warden Ave.. 8uHaro, New York 14225 IPS-798 TABLE OF CONTENTS Section Title Pacae 1.0 Scope 2.0 Applicable Documents 3.0 Class 1E Equipment Being Qualified 4.0 Equipment Per formance Specifications 5.0 Test Procedure 6.0 Specific Features To Be Demonstrated by Testing 7.0 RTD Test Assemblies 8.0 Initial Calibration 9.0 Age Conditioning 10.0 Post Age Conditioning Testing 11.0 Irradiation
- dr, 12.0 Post Irradiation Testing t 13.0 Seismic. Testing t
14.0 Post Seismic Testing 15.0 Design Basis Event-Environmental Test {D.B.E.)
16.0 Post Design Basis Event-Environmental Test {D.B.E.)
- 17. 0 Summary 18.0 Supplementary Data Sections
CONAX CORPORATION 2~p Warden Ave.. Buffalo. New York 14225 IP 1,0 The purpose of this document is to record the IEEE-323-74 t~y Qualification performed by Conax Corporation on a Conax RTD Assembly.
- 2. 0 APPL I CABLE DOCUMENTS
'Pb 2.1 Conax Cor oration F(~r(
Drawing 7138-10000 RTD Assembly Drawing 2399-9627 Seismic Test Fixture
$ ,
Drawing 2316-9626 Prototype RTD Assembly IPS-325 Design Qualification Material t
Test Report for Materials used 1$ in Conax Electric Penetration Assemblies and Electric Con-ductor Seal Assemblies IPS-799 Seismic Vibration Test Report for IEEE-323-74 Qualified RTD Assemblies with Electric Conductor Seal Assembly IPS-781 IEEE-323-74 Qualification Test Procedure for Conax RTD Assemblies 2.2 Standards IEEE Std. 323-1974 IEEE Standard for Qualifying Class lE Equipment for Nuclear Power Generating Stations.
IEEE Std. 344-1975 IEEE Recommended Practices for Seismic Qualification of Class lE Equipment for Nuclear Power Generating Stations
CONAX CORPORATION 2300 Walden Ave.. Buttato. New York 14225 IPS 3.0 CI ASS 1E EQUIPMENT BEING QUALIFIED The actual equipment being qualified is the following RTD Assembly:
Descri tion Conax Part Number Spring Loaded RTD Assembly 7138-10000 The RTD Assembly consists of a dual 100 ohm, 3 wire, magnesium oxide insulated, sheathed RTD probe with polysulfone end seal, a spring loaded extension nipple, Conax Nuclear Service termination head and a eight (8) conductor 18 AWG electric conductor seal assembly (E.C.S.A.) .
- 4. 0
.1 ~1 EQUIPMENT PERFORMANCE SPECIFICATIONS 4.1.1 Accuracy shall be 1.5oF at 212 F.
+ 1.0oF at 32oF and +
4.1.2 Insulation resistance of any conductor to sheath shall be 100 megohms minimum at 100V DC at room temperature.
5.0 TEST PROCEDURE
- 5. 1 The test procedure used was IPS-781 in Section 5 of Supplemental Data Section.
6.0 SPECIFIC FEATURES TO BE DEMONSTRATED BY TESTING 6.1 Testing will be performed in order to demonstrate that the subject RTD Assembly will continue to function per design requirements throughout a series of test phases which will simulate conditions which can be expected to occur during its design life.
6.2 The ability of the temperature indicating device to stay within its required tolerances for accuracy will be demonstrated as the primary requirement. In addition, features such as mechanical integrity will be demon-strated during simulated conditions including seismic simulations with no impairment to the function of the test unit.
CONAX CORPORATION 2300 Walden Ave,. Buffalo, New York 14225 Ip 7.0 RTD TEST ASSEMBLY 7.1 The following Conax RTD Test Assembly was assembled per the referenced drawings listed. The prototype assembly is, identical to those in drawing 7138-10000, but was provided with a thermowell to simulate the actual installed condition.
I 7.1.1 RTD Test Part Desi nation Code ~Te Number RTD 2316-9626
t CONAX CORPORATION 2300 We!den Ave.. Buffafo. New York 14225 IPS-798
- 16. 6 Results 16.6.1 D.B.E. Testing performed was in accordance with the guidelines of IEEE-323-74 and showed the ability of subjected test unit to withstand the simulated temperature pressure profile of an actual loss of coolant accident.
17.0 CONCLUSION
17.1 Based on the results of this test program, that Gonax P/N 7'138-10000 RTD Test Unit qualified all it is shown IEEE-323-74 and IEEE-344-75 criteria for safety related equipment for Nuclear Power Generating Stations.
18.0 SUPPLEMENTARY DATA SECTIONS Section 1 - Data Sheets Section 2 - Photographs Section 3 - Radiation Test Report Section 4 Design Basis Event Environmental Test, Report (D.B.E.)
Section 5 Accuracy h .Calibration Data V
Section 6 Drawings Section 7 - Typical OBE h SSE Test Response Curves
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I Published by Chevron U.S.A. inc. to report RGGE Reference-,80 important product technical information. Chew~en Chevron echmc@II BuIIIIetin CHEVROi% ÃK LUBHICAVIS No. 10 la-1-78 Chevron markets a line of Nuclear Radiation Resistant Lubricants - currently A 2 oils and 4 greases for use in envtrorments sub)ected Co high radiation dosages. These specialty products have successfully served the Nuclear <<~dus~~ since the 1950's and to the best of our knowledge represent the only line'f..these products marketed general'Q In the non Ccrrmunist world.
.Because of their expense and lImited application these products are available for sale o~ through the Centra1 Order Desk, Richnord, California. Refer to the Price Book or the Tanporary Salesfax Page attached (Table I) for orderIr~
procedures.
'lee purpose of this Bulletin is Co assist In the handling of techrZcal ard sales Inquiries.
Technical InauIries not covered in this Bulletin should be. directed to Cnevron Reset ch Ccmar v Rrketh ae ces taraa~ venue c .Op tele. 1 2" -4 .1 N'uclear mcUation affects organic lubricants. Any resulting change is genially urxiesirable because lubricant properties are h<<<<hly optImized for a given appl"cation. Thus, it is Important to use radiation-resistant oils ard greases in all applications sub)ected to high doses of destructive nuclear radiation (radiolysis). Certain general effects are cmmon In the racUolvsis of both oils and greases. ChemLcal1y, hydrogen ard other gases evolve, arA unsaturation arA cross-lir~ of the organic molecules take place. Both low and high molecular weight materials are formed. T?m 1arger molecules predcrninate. This is reflected physically in an increase in viscosity ard ultImate geXation as <<llustrated in P~~ e 1. Greases Init~ became softer due Co attack on the thickening agent. also harden as the base oil cross-~<<. This is illustrated in Figure 2. Eventually, they
'Inhere are. many specific radiolpsis effects dependImg upon the cotrposition of a given lubricant. For example, diester base oils, phosphate esters (antiwear tives) and halogenated materials (EP agents), each produce acids at a low radiation dose. Polymers such as polybutenes ard polymethacrylates cleave readi~~
ard thus lose their V.I. ImprovIng function. Silicone antifoam agents are also em~ily dest. oyed. We approxImate order of radiation stabI1ity of organ'c luids used in lubr<<icants is shown in F<<~e 3. Lirtkted Distributicn: Technical Sales Representative es Representatives Others upon Request
Other factors also affect stability. EUgh. arcrratic content promotes good radiation stability. An oxidizing atmosphere is bad, ard increasing temperature lowers the useful life of lubricants. Fluids below polyphenyl ethers in Figure ' can have radiation resistance improved by including selected additives. Our nuclear radiation-resistant lubricants are made from a33qrlarcmatic-type base oils and contain special additives. They retain their physical properties and lubricating ability over a much wider r~~ e of radiation dosage than con-ventional lubricants. Figure 0 ccmpares a resistant oil with conventiorM materials, while Figure 5 ccmpares a radiation-resistant grease with conventioral lubricants. Spec~> radiaticn-resistant lubricants which are usable urder specified dosages are described in Table l. Xnforration on operating limits and nuclear'adiation recomnended uses is included. Tables Zi through V~~ give pertinent test data. Conventional soap-thickened, mineral oil-based greases will generally, withstand about 10"rads. Special conventional greases will withstand doses of at least 10'ads. Ãuch higher doses can be tolerated by the NHR products. Conventioml compounded oils will general~>> take more radiation than shrd.lar greases, but the oils will exhibit wide variations in the doses that they will withstand. This depends on the base material, the additives used, the exposure conditions, and the performarxe property needed in the appMcation. Encl. Figures 1-5 Tables I-VZj: PC/TS 10/78
~ ~
~ ~
',OOO APPROX. SOLIDIFICATION POINT
~ Q IOO 10 WORST OIL cn O. I C)
C/) BEST OIL', -O O.oj I I 0 I 00 I,OOO I 0,000 l00,000 CHROMED, RADIATtON DOSE, megarads F I GURE 1: RADI AT I ON ALTERS Vl SCOS I TY OF OILS CHFVR04 RESEARCH COWPAi!Y'
'Sold by Chevron U.S,A. inc. I f CA L I 0RN I g ZZ Sges78-
@00
/
l ' 400 / C) VJORST GREASE 300 BEST GREASE" o 200 I 100 0 0.1 I 10 100 1,000 10,000 100,000 RADlATION DOSE, megarads F IGURE 2; RADIATION ALTERS CONSISTENCY OF GREASES CHEVRON RESEARCH COMPANY
'Sold by Chevron U.S.A. inc. RICNIOND, CALIFORNIA RZ S98S7g-1
IOOOOO IO GOO Poiyphenyls Polyphenyl Bhers ~
. Alkytaromajics I OOO Polygiycols Dies)et-s Minerai Oi ls IOO Silicates Disiloxanes Phosphates IO Olefins Sili cones DOSE, eegarads FIGURE 3: RAOIATION RESISTANCE OF BASE OILS (APPROXIMATE GELATION POINT)
OIEYROA RESEARCH CANPANY R I C$ 4QIO, GAL I FONl I A RZ 598580-I
F1GURE 4 GAMMA 1RRAD1ATED 01LS NRRO 358 Turbine Lubricant (Mineral Oil) 900 4400 Gamma Dose, Megarads CHEYRON RESEARCH COMPANY RICKHOKD, CALIFORKIA PIi 780276
FlGURE 5 REACTOR lRRADlATED GREASES 4600 Equivalent Negarads
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~,g>> >: Nio NRRG 235 , Aircraft Aircraft Type Grease instrument Sase High Temperature (Diester Oil- Grease Lithium Soap (Mineral Oil-Thickener) Sodium Amate.
Thickener) . CHEVROH RESEARCH COHPAHY RICHNOND, GALIFORKIA PM 780277
.able T TBPORABX SALiSPAX PAGE G
~lROH !KR 144iECARTS I
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~t Badiat4ion Ba4'"educe Descr4otion P. duc Ibmee C 1 7) 10 Recocncnded Use nuclear Radiation Resistant Greases 25586o Chevron HBB Grease -23 o 163
(-10 to 325) P."enid synthetic oil, Antif"'ct'n bearings 159 30 gelling agent, selenide oxidation inhibitor. scdiun anate up to 10,COO ors p~s eccesso
~
ries; has actuaL'.y vithsto~d "or than 30 x 10 rsds in ball bearings operat~~ inside a nuclear rase!ion. 255861 Chev cn >44q Gre'ase i 17 to 93 235 (O to 2OO) 5O Synthetic arcnatic oil, silica Lov speed, hLgh load gelling agent, and selenide;oxi- slLding su.""aces; scr v dation inhibitor. Also contaLrs nechsnL ns; prov'des graphite snd nolybdentca disulfide " residual tubr'cation 'n as "residual lubrican.s." r~te mchinery, e.g., renote elv~s 5891 C evron ~iq Grease 17 to 121 (o to 25o) 5o Synthetic arctic oil, sodium AntiiVcticn bearings up 335 enate gering agent, and sele-nide oxida ion inhibitor. to 10,000 ~; tivating an4 screv valve ac-nechsnis s. 255892 C e~n tPB Grease -17 to 93 509 (0 to 200) 50 A soft (ASTN vorke4 penetration Special product or an en-360 to 380) version of bBBG-335 c~ osed gear t sin'evc containing nolybden~ disu'de. loped for V.LT. ~~es Co. Rock.ord, M, sn4L used at
.Sanford.
Suclear Bsd4ation-Res steat 5L 1 232981 Chev. cn !icLR 0'- -6.7 tc 107 Lov Viscosi y xro Ryd su ~ c p~s xn~ 1C (+20 to 225) 41 SSU at 210 antic oi'lus se- cesscry equi~eat; gear 358 50 trains; coutrcl =echaniw lected polyne"'s (sone scission and o~i c"+ss'<"> 2329S3 "hevron 4RB Oil- -6.7 to 107 50 S6 SSU st .10 to provide 1 "ccn-360 (+20 to 225) stant v scosiry effect; seleoide 4<<L4 4~sA Zn air; can be extended Ln incr. a~sphere. For add'tional Technical Info~at'ha Contact: P".odact Orderir Chevron Besesrch Cctrpany These products are sold F.0.3. RLCLwond, California, fr ight collect 1ud marketing Serrtces vill not be shLpped until a Pachase Order or Telex is in our hands. 576 Standa 4 Avenue Bio~Cd, CA 94802 Place orders elephone (415) 237-4411 U.S.A. Inc. to'hevron Central Order Group P.o. Sox 1272 Rich ond, CA 94802 Telephone (415) 232-7570 Telex No. 3-4410, C.O.G. Bic~mnd
TABLE II Test Data on Chevron NRR Grease 159 Radiation Dose, 10 Rads 0 ASTM .Penetration Worked 60 Strokes ~ 261 330 Worked 100,000 strokes 325 307 500+ 500+ Copper Corrosion, 100 llr. at 212>F. Slight Stain Siight Stain Oxidation, 100 Hr. at 2504F., psi Drop c 9 24 Mater Resistance / Grease Loss 0 Eva oration / 22 llr. at 300'F. 1.7 F 1 22 Hr. at 400<F, 21 18.5 A arent Vlscoslt olses 04F, at 12 Sec- 7000 2600 04F. at 20 Sec-1 5000 2000 Low Tem erature Tor ue Temperature, 4F. -65 0 40 -65 0 40 Starting Torque, g-cm 2767 554 1106
.
554 Running Torque, g-cm 553 185 10,325 369 344 Nav Gear Wear Test, Mt. Loss of Brass Gear 5 Lb. Load, mg/1000 Cycles 2.0 1.8 10 Lb. Load, mg/1000 Cycles 5.7 5.0 Bearin Performance 10,000 rpm, llr. at 3004F. 1577 634 306 265 10,000 rpm, Hr. at 350 F. 279 188 400 195 196
C
~ ~ 8 ~
~ ~
~ f TABLE III In-oile Tests Chevron NRR Grease 159 Time in Materials Testing Reactor, Hoursb Motor Radiation Dose, b No. Total Irradiated 108 Rads 31182 1432 1049 13.7 31183 1432 1049 13 ~ 7 3 1181 3470 2594 34
- a. Test conditions: 0.3-horsepover motor in vertical position rotated at 6500 rpm; bearings were about
'0.6-inch bore and outside diameter of 1.25 inches; bearing balls and races were M-2 high-speed tool steel vith silver-plated separators; bearings vere unshielded and were preloaded to 6 pounds; helium atmosphere.
- b. 1000 Hours represent incident radiation of 13.5 x 10 8 rads plus 3.2 x 1018 thermal neutrons/sq. cm, plus
- 0. 64 x 1016 fast neutrons/sq. cm', this roughly corr es-ponds to 12.9 x 108 rads, ignoring thermal neutrons.
- c. No failure.
Reviewed, 8/77
TABLE IV Test Data on Chevron NRR Grease 235 NRRG-235 Dose~ 10 Rads 0 41 to 45a ASTM Penetration Unworked Worked 60 Strokes 290 379, 388, 397
.
ASTM Drop Point. 4F. 500+ 500+ Bearin Performance in Size 204K Ball Bearing, Hr. to Failure
'.27; 10,000 rpm, 2504F. 248 4,000 rpm, 2004F. 3000 Na Gear Wear Test, Wt.
Loss in mg/1000 Cycles 6000 Cycles at 5 Lb. 0.22c 3000 Cycles at 10 Lb. 0 n0, 1 03c Four-Ball Test
'0 Minutes Wear at 800 rpm Scar Diameter, mm Steel/Bronco, 2 Lb.
Jaw Load 0.23 Steel/Bronze, 5 Lb. Jaw Load 0.76 Steel/Steel, 20 Lb. Jaw Load 0.47
- a. Three separate irradiations; two in air, one in helium.
- b. }iIL-G-3278 spegification calls for mama of 2.5 and. 3.5, respectively.
Reviewed 8/77 NRRG-300 Data
'nated
TABLE V a Test Data on Chevron NRR Grease 335 NRRG-335a Dose~ 10 Rads 3.8 8.9 26. 2 30.0 ASTM Penetration Unworked 276 257 238 246 221 Worked 60 Strokes 289 289 308 400 359 ASTM Drop Point, oF. 500+ 500+ 500+ 500+ 500+ Bear in P er formanc e in Size 204 K Ball Bearings, Hr. to Failure 10,000 rpm, 250oF. 763 B 644 10,000 rpm, 300OF. 220 154 155 39
- a. NRRG-509 is a soft grade of HHRG-335. NNHG-509 contains molybdenum disulfide and, has an ASTAAI penetration in the range 360 to 380; the radiation stability of HBPG-509 should be similar although its performance characteristics are different from NRHG-335.
Reviewed. 8/77 iARG-300 Data Discontinued
s I I ~s TABLE VI I I P f nce'ial of Se Oils in S ecification Tests a Specification Re uirements Test Results on CheVron Oils
'c Test or Property Light NRRO-358 NRRO-360 I Report Os90 .94
~Vlscoslt , SSU, at 210'F. 85-200 40.8 85.4 ~V!scoslt , SSU, at 130'F. 70-120 ~ 73 ~Viscoslt , SSU, at 100'F. 800-1500 123 1701 ~Viscoslt , SSU, at O'. 10,000 Max.
~
65 50-100 82 22 Pour Point, 'F -70 to +15 0 to +35 +15 +20 Flash Point, 'F. 200 to 400 325 to 470 280 410 Color c7 4-1/2 .4-1/2 lit:lsts a l lztttlun Ilu. 0 l s3 0.20 0 l0 lbtg. Ill l Nll Corrosion to Copper at 212'F. None None light Tarnis h ~Ash 0.003 Hax. 0.05 Hax. 0 0 Sa onif ication No. 0.5 Hax., 0.5 Hax. 0.35 0.41 ' Carbon Residue, % 0 to 0.80 1.2 Hax. 0 ~ 11 0.10 Nature of Carbon L and Fb L and F L and F and F Total Sulfur, % 0.50 Hax. 0.50 Max. 0.41 0.44'race Preci itation No. 0.01 Hax. 0 1 Max. Trace ~Foamln (Af'tat 10 Uinctas) 300 ml 200 ml Pass Not Pass Emulsion at 130'F. (After 30 H inutes) Stable Not Pass Oxidation Corrosion (168 Hours at 2504F.) Evaporation Loss, 7. 1.3 0.6 Change in 100 F. Viscosity -5 to +20 -0.4 0 Change in Neutralization No. e0.20 +0.03 +0.01 Weight Change mg/cm ; Copper + 0.2 to + 0,6 0. 10 +0.08 mg/cm2; Steel + 0' 0 +0.02 mg/cm; Aluminum + 0.2 0.01 0 mg/cm2 l !agnes ium + 0.2 -0.01 +0.02 mg/cm2; Cadmium + 0' t +0.01 +0.01 Mean llertz Load, kg Turbine Oil Oxidation, colours a Ran, f requirements in 12 military specification lu .ting oils. Re,d Grade 3>~ Dropped 8/77 1 nncn FtnFl flnkv. RD 631436
h TABLE VII Test Data on= Chevron HRR Oils 358 and 360 Chevron HRR Oil 358 Chevron HRR Oil 360 Gamma Dose, 10 Rads 0 4.1 9.0 50.0 0 7.00 12.0 52 A earance of Oil Slt. Clear Cloudy jlaze Color, ASDl 3-1/2 A earance of Hx osure Cr n OK OK Black Black ~Vlsooslr cs at 210'F. 4,43 3.51 3.80 7. 10 17 ~ 2 10. 9 11.0 31.1 cs at 1004F. 25.7 20. 3 22.2 72.2 366 202 198 1155 SSU at 2104FA 40.8, 37.9 38.8 49.5 86.6 62.6 62.9 146 SSU at 1004F. 122 99.2 107 335 '1698 934 917 5370 Viscosit Index 85 22 41 43 24 -13 Co er Corrosion, 3 Hr. at 212'F. lb 2c 2c 2c lb 2a 2a lb
'g Neut ra 1 l zat ion Number, KOH/g lllcro Nil 0.10 0.06 0.02 0.01 0.09 0.06 0.01 Four-Ball Mear Test Scar Diameter in mm; 0.51 0.50 10 kg Load; 30 Min. at 0.51 0.57 1200 rpm; Steel/Steel Pour PoinL, F. +15 -20 -65 -40 +20 -20 0 at 2104F. 31 ~ 1 30.3 "0 631437 Re:d Q/7~
NRRu->59 Data
- Discontin>>erl
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Oear Customer: This Bulletin contains important environmental, health and toxicology informa- CM ~g@60 tion for your employees who recently ordered this product. Please make sure this information is given to them. If you resell this product, this Bulletin should be given to the Buyer. Chevron U.S.A. Inc. Material Information Bulletin t:hevran (Approved "Essentially Similar" to Form OSHA 20, Material Safety Oata Sheet) H
~lan CHEVRON NRR GREASE 159 CMS 255860 TYPICAL COMPOSlTION Alkylbiphenyl (Cyp C20) 82%
Additives and thickeners 1896
-
Selenium <1% EXPOSURE STANDARD No OSHA exposure standard or ThreshoM Limit Value has been established for this mater ial. PHYSIOLOGICAL R HEALTH EFFECTS EMERGENCY Bt FIRST AID PROCEDURES Expected to cause no more. than minor eye
~
Wash eyes with fresh water for at least 15 irritation. ~ ~
~ minutes. If irritation continues, see a doctor.
Skin Expected to produce no more than minor skin Wash thoroughly with soap and water following irritation following prolonged or frequently skin contact. Launder contaminated clothing. repeated contact. See Additional Health Data. Inhalation Not expected to be acutely'oxic by inhala- Since this material is not expected to be an tion. inhalation problem, no first aid pi'ocedures are required. Ingestion Not expected to be acutely toxic by inges- If swallowed, give a large amount of water to tion. See Additional Health Data. drink, make person vomit and call a doctor. Chevron Environmental Health Center/P.O. Box )272, Richmond, CA 94802 cRR-6746lA)(10M-9-79) Printed in U.S.A. Emergency Phone Number (415) 233 3737 h No, 1370 - 1980
'j< ~
r IP
ROCHESTER GAS AND ELECTRIC CORPORAT OgfNNA STATION UNl7 pt GINNA STATION C<3Mk~L'a."9 CONTROLLED COPY NUMBER PROCEDURE NO. A-1811 REV. NO. 4 EQUIPMENT INSPECTXON PERIOD AND LUBRICANT LIST'ECHNICAL REVI K0 PORC REVIEW DATE F 3 $ 3 QC REVIEW Q LI Y ASSURANCE PLA T S PERINTENDENT uua q3 1983 EFFECTIVE DATE QA ~ NON-QA CATEGORY 1 ~ 0 REVX R0ED BY: THIS PROCEDURE CONTAINS 64 PAGES
J
~ \3 J
ftw>.'f e,~ 1
/'
EQUIPMENT LUBRICANT BLDG./ 3 MONTH MAINTENANCE PROGRAM
/FLOOR SURVEILLANCE
- PERIOD PROCEDURE NUMBER I CHECK IINSPECTION EQUIP. NO. MGf4 IPRESSURIZER ROBBINS ECI IMYERS JIB CRANE ICONT/OP IHOIST GEAR CASE IMOBIL DTE OIL 26 I MHE-388-1 AS SPECIFIEDI IOPEN GEARS IMOBILTAC E NO LUBRICATION IHOIST CABLE ION CABLE TROLLEY MOTOR MOBIL COMPOUND IGEAR HOUSING IGG IBEARINGS POST ACCIDENT AIR IMOBILUX EP NO. ll IHANDLING VALVES YEARLY YEARLY NO LUBRICATION IREQUIRED CONTAINMENT RECIRCU-ILATING FANS R MOTORS I A, B, C, 6 D ~
I CHEVRON NRRG 159 I 3M-37 YEARLY YEARLY CONTROL ROD DRIVE )SHROUD COOLING FANS I (lA 6 1B) !CONT/OP 3M-37 YEARLY YEARLY MOTOR I MOTOR BEARINGS CHEVRON NRRG 1591 M-45.2 PM-48
- REFERS TO LUBRICATION INSTRUCTION CODE
-1811: 49 EQUIPMENT LUBRICANT BLDG /
/FLOOR 3 MONTH SURVEILLANCE MAINTENANCE PROGRAM
- PERIOD PROCEDURE INSPECTION NUMBER I 'ERIOD 1A & lB REACTOR CONTAINMENT ICOOLANT PUMP IBASEMENT YEARLY YEARLY INJECTION MATER M-101 ~ 8. B IPUMP BEARINGS ILUBRICATED I F/G/H IMOTOR IMOBIL DTE OIL 25I IM-11 AS.J/K IOIL LIFT PUMP MOTOR ISEALED M-45.2 1A & 1B SUMP PUMPS CONTAINMENT I WEINMAN IBASEMENT M-11.17 YEARLY YEARLY I PUMP BEARINGS IMOBILUX EP NO. 1 I MOTOR IMOTOR BEARINGS ISEALED M-45. 2 I COUPLING IDRY REACTOR COMPARTMENT CONTAINMENT ICOOLING UNITS IBASEMENT 3M-37 YEARLY YEARLY MOTOR IMOTOR BEARINGS ICHEVRON NRRG 159I M-45.2 IFAN BEARINGS ICHEVRON NRRG 1591 P & H HOISTS ON 3 I
REACTOR HEAD ICON/CAVITY AS REQUIRED MOTOR I MOTOR BEARINGS I MOBIL DTE BB M-45. 2 IGEAR CASE IMOBIL DTE BB PM-41
- REFERS TO LUBRICATION INSTRUCTION CODE
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/FLOOR 3 MONTH SURVEILLANCE MAINTENANCE PROGRAM
- PERIOD PROCEDURE INSPECTION NUMBER I PERIOD CONTAINMENT CHARCOAL IFANS & FILTERS I (lA & 1B) ICONT/INTER 3M-38 YEARLY MOTOR IMOTOR BEARINGS ICHEVRON NRRG 159I M-45 '
CHAIN FALLS AND MHE-788 SERIES ILUGALLS N/A IMHE-.788 SERIES AS R EQUIRED QM-1389 YEARLY IFORK LIFTS N/A MAINT. IAS REQUIRED AVT CONDENSATE BOOST- TURBINE I ER PUMPS lA 1B & 1C I IBASEMENT M-ll.33 YEARLY MOTOR IMOTOR BEARINGS IMOBILUX EP NO. 2I M-45.2 IPUMP BEARINGS IMOBIL DTE NO 797I STANDBY AUX FEE1MATER IPUMPS lc & 1D I AUX/ADDITIONI 3M-48 M-1 l. 14 YEARLY MOTOR IMOTOR BEARINGS I MOBIL DTE NO. 797 I M-45.2 IPUMP BEARINGS IMOBIL DTE N0.7971 ICOUPLING IMOBILUX EP NO. 8I PM-42
- REFERS TO LUBRICATION INSTRUCTION CODE
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RGGE Reference 8l t Reference Contents: l. 81 Transamerica Letter from Sump B Level Delaval (GEM) Detectors John W. Davin to Richard A. Baker of RGSE, dated January 9, 1984, certifying that the RGGE detectors, part no. LS 57761, are considered environmentally gualified based on similarity to testing performed on part no. XM-54854.
- 2. Excerpts from Wyle Qualification Test Report No. 45700-1, dated March 25, 1983.
- 3. Excerpts from Qualification Test Report No. 45700-2, Bechtel SNUPPS Test.
- 4. Certificate of Compliance for Boston Insulated Wire part no.
13285-H-002, Cable Type TSP 516 AWG, and lab test reports, letter dated February 3, 1982.
- 5. Certificate of Compliance for BIW part No. 13244-H-007, control cable 7/C-12 AWG, and lab test reports, letter dated April 1, 1982.
RG&E purchase order No. N-EG-21257, dated 12/9/81. Excerpts from BIW Proprietary Report No. B915, "Flame and Radiation Resistant Cables for Nuclear Power Plants", November 1980.
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5'oSvu<g>, f'-A l5834
- 12) 33.r~gr N Y, 3nd Vd VB, BOD <41.773-January 9, 1984 Rochester Gas & Electric Corporation 89 East Avenue Rochester, New York l4649 Attention: Mr. Richard A. Baker
SUBJECT:
Your Order 8N-88-19888 h~~- ~~- LS Our Gems Xnvoice/Order N09662 Gentlemen: This is to certify that the Gems Se'nsors Products furnished on the subject order have been qualified in accordance with Gems interpretation of XEEE323-1974 and XEEE344-1975 and based on the similarity to Gems P/N XM-54854, as outlined in. Nyle Test Report 545700-2. Very, truly yours, j~ g g~~g
'j Tr nsamerica Delavai Components JCB/nj cc: Mr. David Dratwa, Delaval Syracuse
Transamerica Delaval inc TC(".r BBBKGI')08 Gems Sensors Div)s)on Ijlcfavsi Plainviile Connecticul 06062 (203) 677-1311 Telex 99306 0 20 December 1983 Rochester Gas 8 Electric-Corp. 89 East Avenue Rochester, NY 14649 Attention: Richard A. Baker
Subject:
= qualification Test Report 845700-2 Bechtel SNUPPS Test
Reference:
RG 8 E P. 0. O'-EG-19888 G'irma Station Gems'nvoice O'09662 The enclosed qualification Report is the final report as prepared in accordance with Bechtel SNUPPS'equirements. No comments will be allowed regarding this report and no changes will be made except those requested by Bechtel SNUPPS. Any comments or changes made by Bechtel SNUPPS will be submitted by page'only, rather than as a new report. One copy of the report is enclosed. Any additional copies will be supplied only against a separate purchase order at a cost of $ 750.00 each. This report will discontinue the control of Gems'quality Control Manual. The enclosed copy of this letter shall be signed and returned to Transamerica Delaval, Gems Sensors Division within five (5) day after receipt of this report.
?
Pr))fark . Vas 1 Technical Sales/Service HEY:ncm Enc.: Report i/45700-2 Received-Date (1) Copy of Letter By CC: TQI: (412) 343-5666 Title TRANSAMERICA OELAVAL INC. 25e t.(b Lobanan Blvd. Plllaburgh, PA 15234 Tall-Frao Na. (Yl. VA a NY) (1-aee-441-7T33)
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NUCLEAR QUALIFICATION TEST PROGRAM ON A LEVEL TRANSMITTER AND A RECEIVER FOR TRANSAMERICA DELAVAL COWLES ROAD PLAINVILLE, CONNECTICUT 06062
7l.st Report REPORT NO. ru tVYLE JOB NO. CUSTOMER h P. O. NO. Ajar&
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pP..p Sl. PAGE i OF PAGE REPORT 8 .." December 14, 1982 Th DATE Sth h' aIa'. gj shrTNF See Re ferences
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SPECIFICATION (S) p lsYIR in Paragraph 5.0
'r, h T'~ r 1.0 CUSTOMER Transamerica Delaval ADDRESS Cowles Road, Plainville, Connecticut 06062 2.0 TEST SPECIMEN One (1) Level Transmitter and a Receiver 3.0 MANUFACTURER Transamerica Delaval Gems Sensors Div.
4.0
SUMMARY
4.1 Results The Liquid Level Transmitter and Receiver, hereinafter referred to as the test specimen, were subjected to a Nuclear Qualification Test Program to qualify them for use in nuclear power generating stations. The test program was performed as specified in Reference 5.1 and in accordance with Reference 5.2. The results of each test are contained in Paragraph 3.0 of the appropriate sections. S TATE OF ALABAMA Michigan Professional Eng. ~ shel hstsf hO lsts'Sfr for } COUNTY OF MADISON } Reg. No. 23187 Gregory K. Henry PREPARED BY
, bofntt duly slrrom, R. . McCoy, /gfgJg, dopcoes and ys: Tho Information contairod ln this roporl ls tho resutt of comPote and carefull ducted tests a ls to tho best of hla k led truo and correct ln APPROVED BY ll respects . F R. J son S/ gf SUB RI BED and
~ ~
~ mt fore this day of to ~~ WYLE Q. A.
T.. txnson Notary P blic in and for tho State of Alaba t targe. My Commission expires ~ F8 LABORATORIES SCIENTIFIC SERVICES 8( SYSTEMS GROUP HUNTSVILLE. ALABAMA
PAGE NO. TEST REPORT NO. 45700-2 4,0 SU/MARY {Continued) 4.1 Results (Continued) TABrZ I NOTICES OF ANOMALY (NOA) NOA No. 2 - On 9-17-811 at 9:30 p.m., the heating unit failed and the thermal aging chamber was turned off. The unit was repaired and at 10:55 a.m. on 9-18-81 the thermal aging chamber was turned back on and the pxogram continued. NOA No. 3 - On 9-30-81 at 7:30 a.m., the heating unit failed and the thermal aging chamber was turned off. The unit was re-
~
paired and, at. 9:15 a.m. on 10-2-81, the thermal aging chamber was turned back on. The temperature stabilized at 120'C at 10:30 a.m. and the aging program was continued. NOA No. 4 - On 12-4-81 at approximately 2:40 p.m., the redundant control-ler tripped and the temperature decreased below tolerance for approximately 75 minutes. The lowest temperature recorded was 180'F. NOA No. 8 On 12-20-81 at approximately 4:30 a.m., the facility power failed and the temperature decreased below tolerance fox approximately 3 hours. The lowest tempexature recorded was 150oF Reference NOA Nos. 2 through 5 px'esented in Apoendix I of Section IV. Notice of Anomaly No. 1 applies only to the specimen described in Nyle Laboratories'est Report No. 45700-1 and is presented in that report. 4.2 Conclusions All tests in this Qualification Program were successfully completed. The Notices of Anomaly were examined and were found to have no effect upon the qualification status of the test specimen. Based upon the successful performance of the Level Txansmitter and Receiver with the Wyle Laboratories-supplied interconnect cable, the Transamerica Delaval Level Transmitter and Receiver can be considered qualified to the requirements of Qualification Plan 45102-2, Revision B, pxovided a qualified interconnect cable is used for equipment interface. LNYLE LABORATORIES Hvntsvillo Facility
PAGE NO. XII-1 TEST REPORT NO. 45700-2 SECTION XII ACCIDENT QUALIFICATION (LOCA/MSLB) REQUIREI KNTS The level transmitter shall be subjected for a period of 30 days to the LOCA/MSLB accident conditions of Figure XII-1 on a best-effort basis. The composition of the chemical spray is as follows: o Boric Acid (.28 molar) o Sodium Thiosulfate (.064 molar) o Sodium Hydroxide (as required to make a pH of 11.0 maximum for the first 2 hours of the test and 8.5 to 9.0 thereafter) The chemical spray shall be sprayed vertically downward at a rate of 0.15 (gal/min)/ft2 of area of the test chamber projected onto a horizontal plane. Spray initiation shall begin l20 seconds into the second ramp and continue for the duration of the test,. Test Item Mountin and Orientation A level transmitter (Type XM-54854) shall be attached to a Wyle-fabricated test fixture, utilizing mounting hardware supplied by the equipment supplier. The transmitter shall be inserted into a Wyle LOCA chamber. Penetxations will be utilized along the LOCA chamber wall to allow for passage of the Wyle-supplied cable to the test specimen. The flex conduit free end will connect to the chamber wall, thus protecting the cabling from the accident environment. All pene-txations shall be potted with Scotchcast 9 epoxy. The transmitter float position shall be fixed throughout the duration of the LOCA test at the "1/2" position. The level transmitter shall be electrically connected to the receiver (Type RE-36520) during the test. The receiver shall be at room ambient conditions. Instrumentation The chamber pressure shall be measured with a pressure transducer in combination with a pressure gauge. "The temperature of the chamber shall be measured thxough the use of three (3) thermocouples. The thermocouples shall be positioned along the centerline of the chamber in such a way as to be within 2 inches of the testspecimen. Individual thermocouple. readings shall be documented utilizing a Fluke 2240 data-logger or equivalent. These readings shall then be averaged and that WYU-: LABDAATDAIES Huntsville Faclllly
PAGE NO. XII-2 TEST REPORT NO. 45700-2 REQUIREMENTS (Continued) Instrumentation (Continued) average utilized for temperature control. The pH of the chemical spray shall be recorded prior to=each ramp and on a daily basis there-after. The flow rate of the chamical spray shall be recorded daily from a flow meter. The chamber temperature and pressure shall be recorded on a datalogger at 30-minute intervals, except during ramps when it shall be operated at its peak rate. The chambex temperature shall be continuously recorded utilizing a pen chart recorder. Electrical Powerin Electrical power of 115 VAC (+58), 60 Hz, shall be provided for operation of the receiver module. The receiver module shall be electrically connected to the level transmitter for the duration of the test. Electrical tfonitorin Five (5) electrical monitoring channels shall be recorded on a datalogger to monitor the electrical operation of the test items. These channels shall be used to monitor the input voltage (115 VAC (+5%], 60 Hz) and the high and low alarm outputs of the receiver module. Two (2) channels on the datalogger shall be provided for recording chamber pressure and temperature. These readings shall be recorded at 30-minute intervals, except duxing the ramps, when the datalogger shall be operated at its peak rate. A pen chart recorder shall be used to continuously monitor chamber temperature. In addition, receiver module meter xeadings shall be taken at each ramp and, as a minimum, once per day. Submer ence Test Following completion of the LOCA/MSLA simulation, the submergence test shall be performed. The Nyle LOCA chamber shall be filled to a height above the J-box using chemical spray solution as the medium. Pressure shall then be applied using GN2 as a pressure source to simulate a depth of 15 feet at the top of the J-box. The submergence test duration shall be 30 minutes. WYLE LABORATORIES Munlsvillo Facility
PAGE NO. XIX-3 TEST REPORT NO. 45700-2 2.0 PROCEDURES The transmitter was installed in the LOCA chamber and "Tefzel" insulated wire was used to replace the tlyle-supplied wire used in the previous phases of the test program to eliminate the possi-bility of the wiring causing an apparent specimen failure. The splices were insulated with Raychem NCSF-70/250-N heat:-shrinkable tubing and the wires were routed through the chamber penetration. The conduit was left disconnected from the chamber wall and the wires exposed to the LOCA conditions to provide qualification to the worst-case mounting configuration. The float level was fixed by clamping a tubular aluminum spacer to the shaft and allowing the float to rest on top of the spacer. The spacer was 45 + 1/8 inches long. The receiver and transmitter were electrically connected by passing the Tefzel wire through a Scotchcast penetration and connecting the Cannon connector to the appropriate connector on the receiver. The required temperature/pressure transients were accomplished by the injection of superheated steam and compressed air. The chemical spray was injected into the chamber through a fog nozzle which pro-vided a uniform spray pattern as projected onto a horizontal plane. The flow rate was monitored using an orifice-type flowmeter and a differential pressure transducer. The transducer output was recorded on the datalogger to continuously monitor the flow rate. The pH of the chemical solution was monitored daily with Litmus paper and adjusted as necessary by adding sodium hydroxide. After the 2-hour mark of the second transient, the temperature was maintained by injecting saturated steam and the pressure was maintained by injecting compressed air. The accident conditions were maintained for a total of 30 days. Following the LOCA test, the submergence test was performed as re-quired by Paragraph 1.0. The test chamber was filled with chemical solution, as described in Paragraph 1.0, until the top of the junction box was covered. The chamber was then sealed and pressurized to 6.5-7.0 psig (15-16 ft H20) at the top of the specimen. The pressure was maintained for 30 minutes. NYLE LABORATORIES Kuntavilio Facilliy
PAGE NO. XII-4 TEST REPORT NO. 45700-2 3.0 RESULTS The accident (LOCA) test required by Paragraph 1.0 was performed as specified in Paragraph 2.0. The LOCA test was conducted for 30 days. During this test, the alarm output, the slave meter reading, and the receiver meter remained within the acceptance tolerances (reference Paragraph 1.4 of Section I of this report) for the duration of the accident simulation. I'n "information only" functional test was performed following the LOCA exposure. The results of those tests are presented on Data Sheets in Appendix III of this section. Following the LOCA test, the submergence test required by Paragraph 1.5 was performed as specified in Paragraph 2.0. The required and actual temperature/pressure profile of the LOCA/MSLB test is presented on Figure XII-1 in Appendix I of this section. Photographs which show the test equipment used during the accident test and the specimen condition following the test are presented in Appendix II of this section. H Instrumentation which were used to obtain data during the LOCA/MSLB test and the additional functional test performed after LOCA are listed on Instrumentation Equipment Sheets presented in Appendix IV of this section. I LA/YLE LABORATORIES Muntsvillo Faclllty
4 PAGE NO. XIII-1 TEST REPORT NO. 45700-2 SECTION XIII POST-ACCIDENT QUALIFICATXON TEST FUNCTIONAL TEST AND POST-TEST INSPECTION 1.0 REQUIREMENTS Post-Accident uglification Test Functional Test The functional test of Paragraph 1.0 of Section III shall be per-formed to determine the extent. of the degradation incurred by the specimen during the accident qualification test. The specimen shall meet the acceptance criteria of, Paragraph 1.4 of Section I. 1.2 Post,-Test Ins ection
.Upon completion of the qualification program, the equipment will be visually inspected. The equipment will be disassembled to the extent necessary to perform the inspection. The condition of the equipment will be recorded. The test equipment disassembly shall include re-moving the J-box cover. The condition of the Dow 710 silicone fluid and the Wyle-supplied cable shall be annotated. Any signs of degrada-tion shall be noted and a statement made as to whether the degradation was greater than, less than, or equal to the degradation experienced by the cable which was not immersed in the fluid.
2.0 PROCEDURES The functional test required by Paragraph 1.0 was performed as speci-fied in Paragraph 2.0 of Section XII. The J-box cover was removed and the silicone fluid and cable were visually inspected. 3.0 RESULTS The functional test was performed and the receiver output recorded. The spe'cimen met the acceptance criteria of Paragraph 1.4 of Section I. WYLE LABORATORIES Huntsville Facility
PAGE NO. XIII-2 TEST REPORT NO. 4S700-2 3.0 RESULTS (Continued) The silicone fluid in the J-box had darkened in color during the test program but remained translucent and liquid. The Wyle-supplied wire which was immersed in silicone oil (and therefore not replaced prior to LOCA) had minute cracks in the insulation, but was otherwise flexible and not discolored. The wire which was removed prior to LOCA was in the same condition as described above.
'Data obtained during the post-accident qualification test functional test is contained on a Data Sheet presented in Appendix I of this section.
Equipment used to record data during the post-accident. qualification test functional test are listed on an Instrumentation Equipment Sheet presented in Appendix II of this section. lhlYLE LAHOAATOAIES Huntsvilto Faclllty
Transamer)ca Delaval Inc. Gems Sensors Division Plainville, Connecticut 06062 (203) 677-1311 Telex 99306 25 Harch 1983 Rochester Gas & Electric 89 East Avenue Rochester, NY 14649 Attention: Dick Baker Engineering
Subject:
l<yle Report No. 45700-1 Bechtel SNUPPS Test
Reference:
Robert E. Ginna P. 0. rIN-EG-19888 The enclosed qualification Report is the final report as prepared in accordance with Bechtel SNUPPS'equirements. No comments will be allowed regarding this report and no changes will be made except those requested by Bechtel SNUPPS. Any comments or changes made by Bechtel SNUPPS will be submitted by page only, rather than as a new report. One copy of the report is enclosed. Any additional copies will be supplied only against a separate purchase order at a cost of $ 750.00 each. This report will discontinue the control of Gems'quality Control Hanual. Final drawings are being prepared and will be submitted by 31 Harch 1983. The enclosed copy of this letter shall be signed and returned to Transamerica Delaval, Gems Sensors Division within five (5) days after receipt of this report. ~~~.gg~ John T. Pech Sales Correspondent JTP:ncm Enc.: Report 845700-1 Received Date One Copy of Letter By CC: Tel: (412) 343-5666 Ti tl e TRANSAMERICA DELAVALINC. 250 Ml. Lobonon Blvd. Pittsburgh, PA 15234 Toll-Froo No. (W. VA
- NY)
(1-800-441-7733)
~TORKS SCEMTlFK: SEfMCES ta SYSTEMS GAOU7
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NUCLEAR QUALIFXCATXON TEST PROGRAM A LIQUXD LEVEL TRANSMITTER AND RECEX VER FOR USE IN THE STANDARDIZED NUCLEAR UNXT POWER PLANT SYSTEM (SNUPPS) FOR TRANSAh1ERICA DELAVAL COWLES ROAD PLAINVILLE, CONNECTXCUT 06062
I'iI='0! hocsssr EhruolvYNnrss ov "fioslhtl j 7eS< RePCI.f y"'.';:
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'YLE REPORT NO.
CUSTOMER P. O. NO. JOB NO. 45700-1 45700 14410 PAGE i OF PAGE REPORT DATF December 8, 1982
'
p SPECIFICATION (S) in Paxagraph 5.0 v's rJ f e CUSTOMER Transamerica Delaval 1.0 DDRESS Cowles Road, Plainville, Connecticut 06062 2,0'EST SPECIMEN One {1) Level Transmitter and Receiver Transamerica Delaval Gems Sensors Div. 4.0
SUMMARY
4.1 Results The Liquid Level Transmitter and Receiver, hereinafter referred to as the test specimen, were subjected to a Nuclear Qualification Test Program to qualify them for use in the Standardized Nuclear Unit Power Plant System (SNUPPS). The test pxogram was performed as specified in Reference 5.1 and in accordance with Reference 5.2. The results of each test are contained in Paxagraph 3.0 of the appropriate sections. STATE OF ALABAMA. Michigan Professional Eng. yysss shsa have no lstyiry ter tSsnscss crsny txxr to person or tropsrry.trc46ntt SPsoLSlor IhiS rcpcrt COUNTY OF MADISON ~ Reg. No. 23187 PREPARED BY Gregory K. Henry being duly swam, R C. McC , r. os and says: The Information containod in thfs report ls tho result ol complete rofut ty.crIadIfcIed tests nd ls to the best of his no)t fedgo truo and correct in APPROVED BY of, nson r WYLE Q. A. SUBS AIBED and sworn r ~ f day 1 R. Stinson
- hfotary blic ln and for fho Stato of Ataba at large.
My Commission expires ~r
/'S , 19 FvvVLK LABORATORIES SCIENTIFIC SERVICES 8( SYSTEMS GROUP
PAGE NO. v TEST REPORT NO. 45700-1 0 '.2
SUMMARY
(Continued) Conclusions All tests were successfully performed with the exception of the Loss-of-Coolant Accident/Main Steam Line Break (LOCA/MSLB) test. NOA's were examined and with the exception of NOA No,. 7, all were found to have no effect upon the qualification status of the test specimen. NOA No. 7 refers to an out-of-specification condition which occurred during the LOCA accident when the x'eceiver output and metex reading were out-of-specification low. In addition, NOA No. 7, Revision A, refers to an out-of-specification condition on the functional test performed after the LOCA and before the submergence test. This functional test was not required by Qualifi-cation Plan 45102-1; however, it was performed to verify equipment condition prior to the submergence test because of the out-of-specification conditions encountered during the LOCA functional test. The specimen cannot be considered qualified to the Loss-of-Coc" ant Accident in the test configuration of Qualification Plan 45102-1, Revision C. This test configuration included Bechtel- (SNUPPS) IO supplied interconnect cable utilized for equipment interface. See Section 3.1.2.1 of Reference 5.2. In a test on an identical Trans-america Delaval txansmitter with a Hyle Laboratories-supplied Tefzel-insulated cable which was installed new and was not irradiated or aged (see Qualification Plan 45102-2, Revision A, and Test Report 45700-2). The specimen functioned properly throughout the LOCA and the subsequent functional tests. Although the exact cause of failure is unknown, that the Bechtel-supplied interconnect cable precipitated the it is very probable failure of the specimen on which it was installed. been supplied to Hyle as "Pre-qualified" and no aging analysis was The cable had performed before the specimen (and cable) was subjected to thermal aging and irradiation prior to the subsequ nt LOCA test. The cable had become cracked, discolored, and very brittle during thermal aging, as documented in NOA No. 6 presented in Appendix I of Section V. Although the anomalies discussed above occurred, the Level Transmitter and Receiver can be considered qualified to the requixements of HLQP 45102-1, Rev. C, provided that a qualified interconnect cable is used for equipment interface. This is based upon the successful performance of an identical (with the exception of mounting bracket) transmittex'ith a Hyle-supplied interconnect cable as documented in Hyle Laboratories Qualification Report No. 45700-2. WYLE LABORATOAlES Huntsvilto Facility
PAGE NO. II-1 TEST REPORT NO. 45700-1 SECTION II RADIATION EXPOSURE 1.0 REQUIREMENTS Transmitter XH-54852A The radiation requirement for the level transmitters is the normal dose of 6x10 rads plus the accident dose of l.lxl08 rads (a 10% conservatism mar in was added) for a total dose o 1.16xlO rads total integrate dos The first 1,000 rads of exposure shall be performed with the receiver in the chamber. The remaining exposure shall be performed with the transmitter only in the chamber, while powered to the receiver. As a minimum, the receiver module input voltage and output current, as well as the "pointer" position, shall be recorded once per day after the first 1,000 rads.
- 1. 2 Receiver RE-36562 The radiation requirement for the receiver module is the normal dose plus the accident dose (a 10% conservatism margin was added), for a total of l.lx103 rads total integrated dose.
I The receiver shall be connected to the transmitter and both units exposed to a minimum total integrated dose of lxlO rads gamma, air equivalent, using a Cobalt 60 source. The float shall be in the "1/2"
~
position; 115 VAC (+5%), 60 Hz, shall be applied to the receiver. The converter output shall be observed during the radiation exposure and the input voltage and output current (approximately 12 mA) shall be recorded before, at least once during, and after irradiation. 2.0 PROCEDURES The specimen was shipped in a Nyle vehicle to the Georgia Institute of Technology Neely Nuclear Research Center for the required irradiation. The specimen was assembled by Hyle personnel in the configurations required by Paragraph 1.0. The irradiation was conducted by Georgia Institute of Technology personnel as described in the Letters of Certification presented in Appendix II of this section. The specimen was monitored before, during and after the irradiation, and the data obtained was recorded on Data Sheets which are presented in Appendix IV of this section. WYLE LA80RATORIES HuntsviHo Facility
PAGE NO. II-2 TEST REPORT NO. 45700-1 3.0 RESULTS The specimen was irradiated as required by Paragraph 1.0, and the irradiation was performed as specified in Paragraph 2.0. The specimen complied with the requirements of Paragraph 1.4 of Section I. During the radiation exposure at Georgia Institute of Technology, the level transmitter was bumped during manipulation of the gamma source, causing the transmitter to fall from its vertical position and strike a table. The only visible damage to the transmitter was a dent in the flexible conduit. Approximately one teaspoon of oil leaked from the J-box. Reference Notice of Anomaly No. 1 presented in Appendix X of this section. Photograph XI-1 shows the extent of damage incurred during the fall. This photograph is presented in Appendix XXX oi this section. Letters of Certification which document the irradiation performance are presented in Appendix XX of this section. Data Sheets which contain data obtained during the daily monitoring are presented in Appendix IV of this section. The equipment used to obtain data during the daily monitoring of the specimen is listed on an Instrumentation Equipment Sheet presented in Appendix IXI of Section X of this report. WYLE LABORATOAIES Hunlsvillo Facility
PAGE NO. III-1 TEST REPORT NO. 45700-1 SECTION IIX POST-RADIATION FUNCTIONAL TEST 1.0 REQUIREYENTS Following the irradiation, one of the two 5-feet sections of flex conduit shall be removed. A syst: em level functional test shall be performed to determine the extent of any damage incurred during the radiation exposure. The specimen shall comply with the acceptance criteria contained in Paragraph 1.4 of Section I of this report. 2.0 PROCEDURES 2.1 Functional Tests fox RE-36562 and XM-54852A The subject. equipment was evaluated utilizing the following syst: em level functional test procedure:
- 1) Connect all electrical plugs and cables on the receiver and transmitter.
- 2) Mith the "ON-OFF-FULL REF" toggle switch in the "OFF" position, zero the meter, utilizing the pointer set scxew adjustment. If not required, this step may be omitted. Document or is not performed.
if zeroing is
- 3) Adjust the receiver voltage input to 115 VAC (+5%).
- 4) Hold the "ON-OFF-FULL REF" toggle switch on the receiver module to "FULL REF" while performing Step 5.
- 5) Adjust the "Calibrate" pot on the receiver module until the meter reads full scale. Xf not requix'ed, this step may be omitted. Document if calibration is or is not performed.
- 6) Position the float on the level transmitter to the "empty" position.
- 7) Record the meter reading. Record the xeceiver module converter output. The output shall be 4 to 20 milliamperes into a 100 to 800 ohm load.
"full" l 8) Repeat Steps 4) and 5) fox the positions, utilizing "1/4", "1/2", "3/4",
the spacer bars manufactured line functional calibration. and for the base-WYLE LABORATORIES Huntavllto Facility
PAGE NO. XII-2 TEST REPORT NO. 45700-1 PROCEDURES (Continued) 2.1 Functional Tests for RE-36562 and XM-54852A (Continued)
- 9) Repeat Steps 3) through 6) for each voltage variation extreme.
The low voltage will be 105.8 VAC (-5 +0). The high voltage will be 124.2 VAC (-0,+6). 3~0 RESULTS The post-radiation functional test required by Paragraph 1.0 was performed as specified in Paragraph 2.0. An additional insulation resistance test was performed on the cable to determine if any damage was sustained in the fall at Georgia Tech. The insulation resistance was in the range of 10 0 ohms, which indicated that the cable suffered no damage The specimen complied with the requirements of Paraqraph 1.0 with the exception of the "Full" and "3/4" positions of the level transmitter. Reference Notice of Anomaly No. 10 presented in Appendix I of this section. The data obtained during the post-radiation functional test is contained on Data Sheets presented in Appendix II of this section. The equipment used to obtain the data in this test is listed on an Xnstrumentation Equipment Sheet presented in Appendix XXI of this section. N VLF. LABOAATOAIES Huntsvlllo Facility
PAGE NO. IV-1 TEST REPORT NO 45700-1 SECTION XV THERMAL AGING AND OPERATIONAL CYCLING 1.0 REQUIREMENTS The level transmitter shall be thermally aged for 90 days (2,161.3 hours) at 120 C and uncontrolled relative humidity. The receiver module shall be thermally aged for 59.15 days (1,420 hours) at 100'C and uncontrolled relative humidity. Operational cycling will be performed on the system level. The level switch and the level transmitter/receiver module will be cycled for 220 cycles each, as specified by Bechtel Power Corporation (a 10$ conservatism margin has been added). A cycle is defined as manually moving the float from the bottom stop to the top stop and back to the bottom stop. The receiver module/level transmitter will be electrically connected and powered with 115 (+5%) VAC, 60 Hz. Operational cycling shall be performed following completion of thermal aging. 2.0 PROCEDURES The transmitter and receiver were installed in separate chambers and were thermally age'd by exposure to the time at temperature required by Paragraph 1.0. The cycle aging was accomplished by attaching a cord to the bottom of the float and manually raising it to the top of the transmitter shaft 220 times. The receiver was connected and powered during this cycling and the meter was observed for full-scale deflection. 3.0 RESULTS The aging program required by Paragraph 1.0 was performed as speci-fied in Paragraph 2.0; During the course of the thermal aging program, the chamber which contained the transmitter was below the temperature requirement for 95 hours and 40 minutes due to heating unit failures., The heater was repaired and the transmitter was exposed to the total (accumulated) time at temperature required by Paragraph 1.0. Reference Notices of Anomaly Nos. 2, 3, 4 and 5 presented in Appendix I of I i this section. The receiver was exposed to the required time at temperature with no interruptions. l WVCL= mBOamaniES Huntsvlllo Facility
PAGE NO. TEST REPORT NO. 45700-1 3.0 RESULTS (Continued) Photographs of the transmitter and receiver, installed in their respective thermal aging chambers, are presented in Appendix II of this section. Equipment used to record and control the temperature during the thermal aging program are listed on an Instrumentation Equipment Sheet presented in Appendix III of this section. INYLE LABORATORIES Huntsvmo Fsclllly
PAGE NO. TEST REPORT NO. 45700-1'ECTION V POST-AGXNG FUNCTIONAL l.0 REQUIREMENTS The functional test of Paragraph 1.0 of Section XXI shall be per-formed to determine cha extent of the degradation incurred by the specimen during the aging program. The specimen shall meet the acceptance criteria of Paragraph 1.4 of Section X. 2.0 PROCEDURES The functional test required by Paragraph 1.0 was performed as specified in Paragraph 2.0 of Section XXX. 3.0 RESULTS The functional test was performed and the rece'iver output recorded. Following the thermal aging, the Bechtel-supplied cable was dis-colored, cracked, and very brittle. Reference Notice of Anomaly No. 6 presented in Appendix X of this section. At the Customer's direction, the cable. remained attached to the specimen for the remainder of the test program. During the post-aging functional test, all measured data was within the acceptable limits as established in Paragraphs'.4.1 and 1.4.2 of Section I. This data is tabulated on a Data Sheet presented in Appen-dix IIX of this section. Photographs which depict the condition of the cable after thermal aging are presented in Appendix II of this section. Equipment used to record data during the post-aging functional test are listed on an Instrumentation Equipment Sheet presented in Appendix IV of this section. lMYLE LABORATOA(ES Huntsvltto Fat:titty
PAGE NO. TEST REPORT NO. 45700-1 SECTION X SEISMIC SINJLATION REQUIRFMNTS S ecimen Mountin The specimens shall be mounted on Wyle-fabricated wall mount test fixtures as snown in Figure X-1. The level transmitter shall be mounted to the test fixture using four (4) 1/2" dia.-l3 x l-l/2" long Grade 5 bolts, washers and lockwashers which shall be torqued to 250 in.-lb> the modular receiver shall be mounted to the test fixture using four (4) 5/16" dia.-l8 x 1" long stainless steel bolts, washers< lockwashers and nuts, which shall be torqued to 150 in.-lb. The specimen/fixture configurations shall then be placed on the Hyle Multiaxis Seismic Simulator Table such that the front-to-back axes of the specimens shall be colinear with the horizontal excitation of the test table. For the second orientation, the specimen/fixture configurations shall be rotated 90 degrees in the horizontal plane to the side-to-side axis and the specified sequence of tests shall be repeated. The test fixtures shall be welded to the table in each orientation. The mounting of the specimens shall simulate their. actual in-service mounting configurations as closely as practical. To account for the effects of the uniform mass of water (0.0443 lb./in.) on a submerged level transmitter, four lengths of 1/4" dia. standard hoist wire rope (which, including the tape used for tie-down, approxi-mately constitute the required simulated weight) shall be taped to the stem assembly of the level transmitter prior to seismic testing. Resonance Search A low-level (approximately 0.2 g horizontally and vertically) biaxial sine sweep from 1 to 40 Hz shall be performed in each test orientation to establish major resonances. The sweep rate shall be two octaves per minute. Transmissibility plots of the specimen response accelerometers from the resonance search test in each orientation shall be provided. Random Multifre uenc Tests The specimens shall be subjected to 30-second duration biaxial multi-frequency random motion which shall be amplitude-controlled in one-third octave bandwidths spaced one-third octave apart over the frequency range of 1 to 40 Hz. Two simultaneous, but independent, random signals shall be used as the excitation to provide phase-incoherent horizontal and vertical motions. The amplitude of each one-third octave bandwidth shall be independently adjusted in each axis until the Test Response WYLE LABORATORIES Huntovlllo Facility
C' PAGE NO. X-2 TEST REPORT NO. 45700-1 1.0 REQUIREMENTS (Continued) 1.3 Random Multifre uen Tests (Continued) Spectra (TRS) envelop the Required Response Spectra (RRS) . The resulting table motion shall be analyzed by a response spectrum analyzer at five percent (5%) damping, and plotted at one-third octave intervals over the frequency range of 1 to 200 Hz. Five (5) Operating Basis Earthquake (OBE) tests, followed by one (1) Safe Shutdown Earthquake (SSE) test, shall be pexformed in both the front-to-back/vertical (FB/V) and the side-to-side/vertical (SS/V) orientations. The OBE and SSE RRS are shown in Figures X-2 and X-3. TRS plots of the control accelerometers from a representative OBE and the SSE test at. 5S damping in each test orientation shall be pxovided. 1.4 S ecimen Res onse Six (6) uniaxial piezoelectric accelerometers shall be mounted on the test specimens to monitor response to the seismic excitation. Place-ment. of these accelerometers shall be as directed by the Wyle Project Engineer. FM tape and oscillograph recorders shall provide a record of each accelerometer's response. TRS plots from the SSE tests, analyzed at 5% damping, shall be included. 1.5 Electrical Powerin Electrical power of 115 (+5%) VAC, 60 Hz, single-phase, shall be pro-vided for opexation 'of the test specimens during the Seismic Test Program. 1.6 Electrical Monitorin One (1) channel of electrical monitoring shall be recorded on an oscillograph recorder to monitor the 4-20-milliampere output of the receiver. 2.0 TEST PROCEDURES The Seismic Test Program consisted of subjecting the test specimens to resonance search testing and qualification level biaxial random multifrequency testing in each of two test orientations, as specified in Paragraph 1.0. The specimens were instrumented with accelerometers, and electrically powered during the test program. KYLE LABORATOAIES Huntsville Faclllty
PAGE NO. TEST REPORT NO. 45700-1 TEST RESULTS The specimens demonstrated sufficient integrity to withstand, with-out compromise of structures or functions, the prescribed simulated seismic environment. The oscillograph monitoring the Receiver output indicated no anomalous output. Table X-I, Appendix I of this section, contains descriptions of the test runs. Figure X-l, Appendix II of this section, shows the mounting concept of the specimens. Figures X-2 and X-3, Appendix II of this section, show the horizontal and vertical OBE and SSE RRS, respectively. Photographs X-1 through X-5, Appendix specimen mounting details. III of this section, show the Photographs X-3 through X-6, Appendix III of this section, show the specimen response accelerometer locations. Appendix IV of this section contains Transmissibility plots from the resonance seaxch tests. Appendix V of this section contains the Test Response Spectrum plots of the control accelerometers from a representative OBE test and the SSE test in each test orientation. Additionally, TRS plots of the specimen response accelexometers from the SSE test in each test oxien-tation are also included. NOTE: The TRS did not envelop the RRS in the frequency range from 1 Hz to 12.5 Hz. However, the obtained TRS constitute the machine limits of the Hyle Biaxial Seismic Simulator for this particular test arrangement. Appendix VI contains the Instrumentation Log Sheets and the Instrumen-tation Equipment Sheets. QlYLE LABORATOA!ES Huntsvilio Facility
B I W CABLE SYSTEMS, tNC. 65 BAY STREET 'OSTON. MA 02125 '617) 265.2102 'ELEX 94-0604 February 3, 1982 Rochester Gas & Electric Corporation 89 East Avenue Rochester, NY 14649 Attention: Purchasing Department Gentlemen: ROCHESTER GAS 8( ELECTRIC P.O. ¹N-EG-21257 BIH JOB ¹1D269 Enclosed is a certificate of compliance, general data sheet and laboratory test report covering BIW part number 13285-H-002, as required by your above mentioned purchase order. If you have any questions regarding this test data, please contact us. Very -truly yours, BIW CABLE SYSTEMS, INC. Francis J. Ellard Chief Inspector guality Control Enclosure
44 a> S 4 g OWJ~+y 1-27-82 Vi -EG-21 57 Rochester Qas i E1ectric 89 East Avenue Rochester, VZ 1.~6~9 I MI I<< ~ P\ BI':J Job -P 19259 3-20011 001 BlN PliV 13285-R-302 '303'SP i 16 AgQ BPST<<D 7i
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B I W CABLE SYSTEMS, INC. 65 BAY STREET BOSTON. MA 02126 i 617) 266 ~ 2102 'ELEX 94.0604 CERTIFICATE OF COMPLIANCE
~ I vI~ ~ V, BIW ORDER NO. CUSTOMER'S ORDEP. NO.
1D269 N-EG-21257 I Ginna Station Constr. SHIP TO 1503 Lake Road Ontario, NY 14519
$ QLD TQ Roches ter Gas & El ectri c 89 East Avenue Rochester, NY 14649 I
DATE 2/3/82 QUANTITY BIW PART DESCRIPTION SHIPPED NUMBER
'300' 13285-H-002 BIN certi fi es thi s i tern i s in compliance with IEEE-383-1974 and the requirements of your purchase order, BIN specifications and 10CFR Part 21 Thi" is to certify that the above material furnished against the above nurchase order number is made in full accordance with the referenced specification(s) and meets all of the requ rements of the specification(s)
Electrical test reports are on file and are available for examination upon request. CHIEF INSPE OR, EQUALITY CONTROL
BIB CABLE SYSTEMS, INC. Bay Street
- Boston - Massachusetts 02125 LABORATORY TEST REPORT DATE: F br ar 3 1982 LAB. TEST NO.: 81I053 CUSTOME Rochester Gas & Electric PURCHASE ORDER~0.: N-EG-21257 BIW P/N: 13285-H-002 f,ABLE i TYPE: TSP ~16 AWG CONTRACT NO.: 10269 SPECIFICATION NO: OA-20, Rev. 3 11-15-78 ITEM NO.: BILL OF MATERIAL NO.:
TESTS PERFORMED ri inal T nsile Stren th & Elonaation (jacket 8 insulation Air Oven A in acket & insulation Set 'acket 0/ 'acket) Oil Immersion A in (jacket) This is to c'erti+ that the following cable furnished against the above order number was tested in full accordance with the referenced specification(s) and meets all of the requirements of the specification(s).
-
Electrical test reports are on file and are available for examination upon request. APPROUED BY" LABORA ORY MANAG AUTHORZZED,'FOR RELEASE BY: QUALITY GGNTROL CHIEF INSPECTOR
BIN CABLE SYSTEt1S, INC. LABORATORY TEST REPORT CUSTOMER: LAB TEST NO 5 CUSTOMER ITEM NO . 2 BlV PART NUMBER 1 2 DATE F r v SPEC
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4" 4 4 INSULATION TESTS CONDITIONING SPECIFIED VALUES MEASURED VALUES Orig. Tensile Str. None 700 psi (min) 1657 psi Orig. Elongation 250% 455% Air Oven Aging 7 days 9 121'C Tensile Strength 75% OT (min) 110% Elongation 75% OE 80% JACKET TESTS TEST CONDITIONING SPECIFIED VALUES MEASURED VALUES Orig. Tensile Str. None 1800 psi {min) 2561 psi Orig. Elongation 300% 340% Air Oven Aging 7 days 9 100'C Tensile Strength 85% OT (min) 108% Elongation 65% OE 78% CABLE TESTS
BIN CABLE SYSTEMS, It<C. LABORATOR'Y TEST REPORT CUSTOMER: Rochester Gas 8 Elec. LAB TEST NO. 81I053 CUSTOMER P 0 N-EG-21257 '. BIW JOB NO
~ NO 10269 CUSTOMER ITEM NO 2 BIW PART KJMBZR 13285-H-002 DATE Februar 3. 1982 SPEC. OA-20. Rev. 3 11-15-78
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INSULATION TESTS CONDITIONING JACKET TESTS CONDITIONING SPECIFIED VALUES MEASURED VALUES Set Hone 30% (max) Stress 9 200% None 500 psi (min) 1317 psi Oil Immersion Aging ,18 hrs. 9 121 C Tensile Strength in ASTM g2 Oil 60% OT (min) 86% Elongation .,60% OE 85% CABLE TESTS TEST REQUIREMENTS
CABLE SYSTEMS, INC. GENERAL DATA SHEET q.C. FORM 017; 4 A CUST.' ster Gas & Electric GUST P 0 8 N-EG-2125 TEM 8 2 BIW T 8 13285-H-002 JOB 8 19269
.8~2-2 . 3 *~23 82 PHYSICAL DATA ELECTRICA DATA LOT SIZE CONTINUITY DIEL I.R. D.C. FA II VOLTAGE RES.
NO INSPECTED SHORTS ITHSTAND NO PASSED REEL LENGTH (110 VAC NO FT BTWN SHLDS) 5 HIN HIN 2500 VAC 3240 62 DESCRIPTION PECIFIED MEASURED MEGn/M'.
.415 HAX
.405 NOM .397 NOM, 001 3300'k ok 16184 n/H'KT.DIA.
4.00 3-20011
.045 NOM JKT TllKN .036 HIN .040 MIN.
INSUL. THKN. .023 MIN .0 5 MIN. JKT. INSUL. THKN..014 HIN HIN. CABLE DESCRIPTION 2 x 816 AWG, 7/.0192" CONDUCTOR TC BIW Cable Systems, Inc. PRINT 2/C II16 AWG 600 Volts Alum-Mylar tape, 818 AWG SIIIELD 7/.0152" TC drain wire Printed COLOR CODE REMARKS: APPROVED BY: Al(A'l T2PV PA 1'Pl)AT 1CAMh&f.I)
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pi ~ B I W CABLE SYSTEMS, INC. 65 BAY STREET BOSTON, MA 02125 (617) 265-2102 TELEX 94-0604 BI% April 1, 1982 Rochester Gas & Electric Corporation 89 East Avenue Rochester, NY 14649 Attention: Purchasing Oepartment Gentlemen: ROCHESTER GAS & ELECTRIC P.O. ¹N-EG-21257 BIW JOB ¹10269 Enclosed is a certificate of compliance, general data sheet and laboratory test report covering BIll part number 13244-'H-007, as required by your above mentioned purchase order. If you have any questions regarding this test data, please contact us ~ Very truly yours, BIW CABLE SYSTEMS, INC. Chief Inspector equality Control FJE/md Enclosure
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E3 I W DWHt E HV'&TEMP, INK. 65 BA Y STREET BOSTON. MA 02:25 (6'?) 265-2102 TELEX 94-0604 CERTIFICATE OF COMPLIANCE BIW INV. NO. BIW ORDER NO. CUSTOMER'S ORDER NO. 10269 N-EG-21257 I Ginna S tati on Construction 1503 Lake Rd. Ontario, NY 14519
+ Rochester Gas 8 Electric 89 East Avenue Rochester, NY 14649 DATE 3/19/82 QUANTITY. PART DESCRIPTION 1100'IW SHIPPED NUMBER 13244-H-007 BIW certifies this item is in compliance with IEEE-383-1974 and the requirements of your purchase order, BIlJ specifications and 10CFR Part 21 ,."Iis is to certify that the above material furnished against the above purchase order number is made in full accordance with the referenced specification(s) and meets all of the requirements of the specification(s)
Electrical test reports are on file and are available for examination upon request. CHIEF INSPEC, UALITY CONTROL
BI'll CABLE SYSTEMS, INC. Bay Street + Boston -'assachusetts 02125 LABORATORY TEST REPORT DATE: A ril l. 1982 LAB. TEST NO.: 82C051 GUSTO Rochester Gas & Electric PURCHASE ORDER %0.: N-EG-21257 BIN P/N: 13244-H-007 CABLE TYPE: Control CONTRACT NO.: 1 D269 SPECIFICATI0N NO.: gA-20, Rev. 3 11-15-78 ITEM NO.: BILL OF MATERIAL NO.: 5-03071 TESTS PERFORMED Ori inal Tensile Stren th & Elon ation (jacket & insulation Air Oven A in acket & insulation This is to certify that the following cable furnished against the above order number was tested in full accordance with the referenced specification(s) and meets all of the requirements of the specification(8). Electrical test reports are on file and are available for examination upon request. APPROVED BY: 77
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LABORATORY MANAGER
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AUTHORIZED FOR RELEASE BY QUALITY CO ROL CHIEF INSPECTOR
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Y' BIN CABLE SYSTEMS, INC. LABCEQZCEY TEST REPORT 0 CUSTCEGZ: CUSTOMER P Rochester 0 NO CUSTGHER, ZCEM NO 1 Gas 5 Electric N-EG-21257 'DJ LAB TEST NO.. JOB NO BIN PART KJMBER 82C051 1D269 1 3244-H=007 QhZE ril 1 SPEC R v CONDITIONING SPECIFIED VALEJES Orig. Tensile Str. N'one 700 psi (min) 2245 ps'i Orig. Elongation . .250% 630% Air Oven Aging 7 days 9 121'C Tensile Strength 75% OT (min) 80% Elongation 75% OE 79%
'MKET WMTS CONDITIONING Orig. Tensile Str. .None 1800 psi (min). 2400 psi Orig. Elongation 300% 350%
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Air Oven Aging 7 days 9 100'C Tensile Strength 85% OT (min) 99% Elongation 65% OE 87%
<CADI E SYSTEMS, INC. GENERAL DATA SIIEET g C. FORkl Ot<<1 GUST. ie CUST. P.O. 4 N-EG-2125 ITEM 8 1 BIW PART 4 13244-H-007 W JOB 41D269 SPEC~ - 0 DATE 8 PIIYSICAL DATA ELECTRICAL DATA LOT SIZE CONTINUITY . DI EL I.R. D.C..
81 VOLTAGE, RES. NO INSPECTED SHORTS WITH STAN NO PASSED REEL LENGTII NO FT CHECK 5 MIN MIN 3500 VAC 2617 DESCRIPTION PEG IFIED MEASURED MEGA/M'.72
.730 MAX
.715 NOM .730 NOM. 002 1100'k ok 15900 n/M'KT.DIA.
1:68 3-20184
.060 NOM JKT. TIIKN. .048 MIN .054 MIN
.030 NOM IWSUL. TIIKN. .027 MIN .030 MIN.
JKT. .020 NOM INSUL. THKN. .016 MIN 018 -'IN. CABLE DESCRIPTION BIW Cable Systems .Inc. (year) 7/C-12 AWG EPR/ HYP Insul, Hyp Jkt, 600V PRINT 7 x 812 AWG, 7/.0305" CONnIICTOR TC SIIIELD n/a COLOR CODE Printed REMARKS: APPROVED BY: P~I 61 'F1~V P 1 1'l)A1 'llhl I hP121)
I'
./ .-Ji~W OillGihI'kill<6DEPT. ~r BXh CMLE SYSTEM PURCHASE ORDER NO.
C5 BM ST. B OSTON, l&. 02125
~i'OCHES1ER 89 EAST AVENUE GAS ANO ElECTRIC CORPORAIION ROCHESTER, NEW YORK 1 J649 ATTENTIOHi PURCHASIHG DEPT.
I CORPORATION ROCHESTER GAS AND ELECTRIC 12-9-81
""- 'I"'"Dl'- A~~GHR,A. BAKER - ENR 3262 DATE ooRm QXNNA STATXON CONSTRUCTION (p,b g~8 <+ l503 LAKE RD ~
CALL 21d ~ Oid 2)00 TEH,U~+~ ANY QUESTIONS SHOULD 8 E DIRECTED TO: DATE REOUIRED 0 DAYS BOSTONP NA IN OUR PLANT ON OR BEFORE 642 J. JONES ,,2324 ATDHcE BIN NO. LIST DISCOIJNT DESCRIPTION IT EM 0U ANT ITY 2413 F 00 1 F000 FT. OF 712 AHG CONTROL CABLE AS 54334-SP DATED 10-26-81 PER BIH QUOTATION FT 516 48m.00 Yi 3,000 FT. OF SXNGLE TWISTED SHXELDED PARR AS PER BXH QUOTATXO AbG XNSTRUllENTATXON CABLE f543@-SP DATED 11>>16-81 NXTH CERTXFXCATE EJ3OVE ITEMS TO BE SUPPLIED TO FULL XZFE 383-1974 FLM1E AND LOC 0'OlGLXANCE TEST REPORTS TEST THE SUPPLXER SlfALL PROVXDE FOR ALL PRODUCTION TESTS SHALT BE CONTROLLED EQUIPARANT TO BE FURNXSHED t1HETING THE A QUALITY ASSURANCE PROGRAM)ll 20 TUPV. 3 REQUXREI&NTS OF ATTACHED PGGE QA ACCOUIIZ WORK ORDER JOS CODE TAX STORE OR CAR CROUP NO. CODE DEPT DIST. STA. CL MAJOR 1 324 00 63-1 6429 0 0 (SKIPPING INFORMATION) EXT AT ONCE ITEM OUANTITY N-60801 DESCRIPTION BIN NO LIST DISCOUNT DATED 11-15-78 CABLE SHALL BZ SHXPPED IN ACCORDANCE 3VITH AH&X 45 '.2 LEVEL C "THE PROVISIONS OF REGULATION 10 CFR PART 21 APPLIES TO TECXS PURCHASE ORDER." TAX CODE STORE NO. DEPT D IS I'CCOUNT CODE STA. CL MAJOR MIII. WORK ORDER OR CAR CROUI'O 08 . 6429 (SHIPPING INFORMATION)}}