ML18078B041
| ML18078B041 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 03/16/1979 |
| From: | Mittl R Public Service Enterprise Group |
| To: | Parr O Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7903200434 | |
| Download: ML18078B041 (16) | |
Text
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I.... 0 PSRJ
- Public Service Electric and Gas Company.BO Park Place Newark, N.J. 07101 Phone 201 !430-7000 March 16, 1979 Director of Nuclear Reactor Regulation U. s. Nuclear Regulatory Commission Washington, D. c.
20555 Attention:
Mr. Olan D. Parr, Chief Light Water Reactors Branch 3 Division of Project Management Gentlemen:
RESPONSE TO REQUESTS FOR ADDITIONAL INFORMATION NO. 2 UNIT SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-311 Public Service Electric and Gas Company hereby transmits 60 copies of its response to the Environmental Qualification items listed in section 8.4~ of the Safety Evaluation Report Supplement 3.
Should you have any questions, please do not hesitate to con-tact us.
Enclosure 7 9 0 3 2 0 0 4 3'(
The Energy People
.vtu;*
R. L. Mi:t General Manager -
Licensing and Environment Engineering and Construction llr>-2001 l400Ml 9-77
8.4.8 Environmental Qualification of Electrical Equipment (1) Electrical Terminal Blocks.
Qualification test plan and test results.
(2) Electrical Cables.
The reports on the additional cable testing performed by the manufacturer.
(3) Motor-Operated Valves.
Additional justifica-tion should be provided, based on Unit 2 containment environmental requirements, for those motor-operated valves which are being reviewed as part of Westinghouse requalif ica-tion program and found unacceptable.
(4) Fan Coolers.
The applicants were informed that WCAP-7829, "Fan Cooler Motor Unit Tests,"
was found unacceptable and that motor hot spot temperature analyses similar to those per-formed for the same equipment in the Diablo Canyon Plant be provided for our review.
ANSWER:
(1) Electrical Terminal Blocks The following is a discription of the qualification test plan:
I.
SCOPE OF TEST The following specifies the test procedure for quali-fying protected electrical terminal blocks for a LOCA and SLB environment.
The test models consisting of junction boxes, terminal blocks, and cable, were assembled at the Salem Nuclear Generating Station in accordance with prescribed installation practices for that plant, and are identical in all respects (except-ing length of conduit connected to box) to such M P79 5 18 1 8.4.8(1)-1
equipment presently planned for service at Salem Unit No. 2.
The test models were assembled using ten,1inal blocks which were not irradiated; however, the tests will be performed with replacement terminal blocks which have been irradiated (See II below).
I I.
'.l:'ES'.2 PRECOlWITIOIHHG A.
Terminal Blocks -
Both the Buchanan 2Bll2!J and 616508-6 blocks were exposed to a Cobalt-60 Garama field at a dose rate of.98 rnegarads per hour for a total of 200.2 rnegarads.
Pre-exposure and post-exposure high potential tests were performed on these terminal blocks.
B.
Cable -
The cable, 9 conductor number 14 wire, has been qualified for 200 megarads exposure though the cable used in this test was not actually exposed to radiation.
III.
MATERIAL TO BE TESTED A.
Individual Items:
- 1.
Four Buchanan Terminal Blocks (Irradiated to 200 megarads) Model 616508-6.
These blocks are marked A, B, C, and D.
- 2.
Eight Buchanan Terminal Blocks (Irradiated to 200 rnegarads) Model 2Bll2N.
These blocks are marked E, F, G, H, I, J, K, and L.
M P79 5 18 2
- 8. 4. 8 ( 1 )-2
e III.
MATERIAL TO BE TESTED (CONT'D.)
A.
Individual Items (Cont'd.)
- 3.
Six galvanized steel junction boxes measuring 13-1/2" x 13-1/2" x 6" with cover.
These boxes are fabricated in accordance with Public Service Electric and Gas Company Drawing number 212805-D-4131, Figure 3.
Each of the boxes is fitted with two 2" close nipples secured with a 2" Meyers scru-tite hub.
- 4.
Twenty four 10' long lengths of 9 conductor number 14 control cable rated for 600 volts.
This cable is manufactured by Triangle P.W.C.
Inc. and was supplied on Manufacturer's Reel No. 17025 (Salem Reel No. S5054).
B.
Assemblies To Be Tested:
Six junction box assemblies each consisting of one junction box, two terminal blocks, and four lengths of cable assembled as per PSE&G Co. sketch E-101278 attached.
These assemblies are to be designated as follows:
Terminal Blocks Assembly Configuration Position l Position 2 l
Left Hand E
F 2
Right Hand G
A 3
Left Hand H
I 4
Right Hand c
J 5
Left Hand K
B 6
Right Hand D
L M P79 5 18 3 8.4.8(1)-3
C d.f. e
- Mo i ications:
- 1.
PSE&G Co. Test Coordinator may modify the test assemblies prior to test initiation.
Modifi-cations can include (but are not limited to) drilling of weep holes, filling of boxes with insulating material, or rearranging terminal block positions.
- 2.
Test assembly quantities may be increased if any tests are aborted due to external circuitry problems.
IV.
PREPARATION FOR TESTING A.
Assemblies are to have their nAs Suppliedn terminal blocks removed.
B.
Irradiated terminal blocks are to be installed in accordance with III above.
C.
Thermocouples are to be mounted on the top of at least one of the terminal blocks and a thermo-couple is to be mounted on the inside surface of the junction box.
(Location to be determined by PSE&G Test Coordinator).
M P79 5 18 4 8.4.8(1)-4
IV.
PREPARATION FOR TESTING (CONT'D)
D.
Thermocouple lead wires are to be run through 2-inch nipples.
E.
Opening of 2-inch nipples are to be sealed using PR-855 fire resistant RTV silicone foam packaged in SEMKIT two part sealant cartridge.
All space in nipples not occupied by cable is to be filled with silicone foam.
V.
TEST -
SERVICE CONDITIONS A.
All terminal points of one block in each test item will be wired to an AC source so as to impress 140 VAC (120 VAC and margin) across neighboring points.
Odd numbered terminal points to carry 2 -
5 a.
B.
The lower six terminal points of the second block in each test item will be wired to a DC source so as to impress 140 VDC across neighboring points.
Line current will be limited to 100 ma.
C.
Test circuitry will be arranged so as to identify single point failures.
M P79 5 18 5 8.4.8(1)-5
e V.
TEST -
SERVICE CONDITIONS (CONT'D)
D.
The above service conditions will be maintained throughout the duration of the test except when circuit insulation resistance readings are being performed.
VI.
TEST PROFILES -
ENVIRONMENTAL CONDITIONS A.
- 1.
125°F @ 0 psig to 286°F @ 50 psig in 10 seconds.
- 2.
Maintain 286°F@ 43 psig until t = 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />,* 47 minutes.
- 3.
15 minutes maximum ramp of 286°F @ 43 psig to 240°F @ 10 psig.
- 4.
Maintain 240° and 10 psig until t~ 240 hours0.00278 days <br />0.0667 hours <br />3.968254e-4 weeks <br />9.132e-5 months <br />.
S.
Duration of the test period to be determined by PSE&G Company Test Coordinator.
B.
Stearn Line Break (SLB)
- 1.
125°F @ 0 psig to 350°F @ 43 minimum psig in 5 minutes maximum.
- 2.
Maintain 350°F and 43 psig until t = 10 minutes.
M P79 5 18 6 8.4.8(1)-6
1-...
- VI.
TEST PROFILES -
ENVIRONMENTAL CONDITIONS (CONT'D)
- 3.
15 minute ramp of 340°F and 43 psig to 240°F and 10 psig.
- 4.
Maintain 240°F and 10 psig until t = 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- s.
Duration of the test period to be determined by PSE&G Company Test Coordinator.
C.
Chemical Spray Spray to consist of 1.2% (By Weight) boric acid solution with sufficient sodium hydroxide added to maintain a pH of 8.5 to 10.0.
Spray rate to be
.15 to.2 gallons/min./Sq. Ft.
Temperature of solution to be established by conditions required to maintain test chamber temperature.
Chemical spray to be initiated 5 minutes after achievement of peak temperature of test profile.
Spray to be maintained for 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> duration.
D.
All the parameters specified in A, B, and C above are to be considered as ideal and any variation of these values must be recorded and their effect evaluated at the end of test.
M P79 5 18 7 8.4.8(1)-7
e VII.
DATA RECORDING A.
Hourly
- 1.
Chamber temperature
- 2.
Terminal Block temperatures
- 3.
Enclosure temperatures
- 4.
Chamber pressure
- 5.
Chamber water level
- 6.
Spray solution flow rate
- 7.
Voltage
- 8.
Line current
- 9.
Leakage currents B.
Prior to beginning of test, and twice daily for the duration of the test, IR @ 500 VDC, point to point and point to ground.
C.
Every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, spray solution pH.
VIII. DESCRIPTION OF TESTS A.
Test 1 - Test assemblies 1 and 2 subjected to environmental conditions noted in VI A (LOCA) and VI C while subjected to service conditions of v.
B.
Test 2 -
Test assemblies 3 and 4 subjected to environmental conditions of VI B (SLB) and VI C while subjected to service conditions of v.
M P79 5 18 8 8.4.8(1)-8
VIII. DESCRIPTION OF TEST (CONT'D)
- c.
Test 3 -
(If required) Test assemblies 3 and 4, modified as directed by Test Coordinator, subjected to environmental conditions of VI A (LOCA) and VI C while subjected to service conditions of v.
This test to be performed in event of failure of Test 1.
D.
Test 4 -
(If reguired) Test assemblies 5 and 6, modified as directed by Test Coordinator, subjected to environmental conditions of VI B (SLB) and VI C while subjected to service conditions of v.
This test to be performed in event that Test 3 is required.
IX.
ACCEPTANCE CRITERIA The assemblies are expected to perform, throughout the duration of the tests, in the mode described in Section V abov~.
If leakage current of any test circuit exceeds 1 ampere, post test examination shall determine the cause of the leakage current, that is, if the failure was in the tested circuit or in the connections to the test circuit.
M P79 5 18 9 8.4.8(1)-9
X.
TEST REPORT A formal test report shall be provided encompassing all tests that were performed.
This test report should include all photographs, drawings and data involved with each test and each post test inspection.
This report and all information regarding the equipment tested is to be classified as Proprietary Information.
The Buchanan terminal blocks and their enclosures were tested as described in the Test Plan and successfully passed the LOCA and MSLB accident condition(Refer to Table Q7.30).
A formal report (Conax Report IPS-400) is being prepared and will be submitted to the staff for review.
M P79 5 10 8.4.8(1)-10
(2) Electrical Cables For those cables not re-tested to the new MSLB peak temperature, the peak surface temperature was calculated by Stone Webster Engineering Corporation utilizing their thermal analysis model.
These calculations were performed using the same method and similar assumptions used for North Anna Power Station of Virginia Electric Power Company.
Two conductor, No. 16 gauge cable geometry and data were provided as the most severe case.
The following test temperature was used.
At t=O the test temperature was 120oF, increasing to and remaining at 350°F for one minute, staying above 300°F for three minutes and dropping to 286°F for the duration of the accident.
With this profile the calculated peak surface temperature of the cable was 333°F.
Cable samples, irradiated with a total dosage in excess of that encountered in a MSLB, had originally been successfully tested at 3400F for approximately three hours.
PSE&G therefore concluded that these and other cables previously tested at 3400F are qualified for use in the containment at Salem Generating Station, Unit No. 2, since the test temperature was higher than the calculated peak surface temperature.
Certain control and instrumentation cables which are manufactured by American Insulated Wire are now being re-tested.
This retest is being performed even though the cables successfully passed the temperature-pressure require-ments, however, the total irradiated dose during the test M P79 5 18 11 8.4.8(2)-1
e*
e was only 100 megarads.
Franklin Institute Research Laboratories is currently performing the retest on both thermally aged and unaged samples with a total irradiated dose of at least 200 megarads.
To date, the samples are approximately thirty-five days into the test cycle and have successfully withstood the most severe initial LOCA transients.
The samples are being maintained at a constant temperature (212°F) for the duration of the test which is expected to be concluded in mid-April, 1979.
Upon completion the qualification test reports and analyses will be available for staffs review.
MP79 5 18 12 8.4.8(2)-2.
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(3) Motor-Operated Valves Westinghouse supplied motor operated valves for in containment use at Salem Generating Station, Unit No. 2 utilizing Class *e* insulation and reliance motors.
The qualification basis was provided in Westinghouse letter NS-CE-692 dated July 10, 1972, to Mr. D. B. Vassello, Chief, Light Water Reactors Project Branch 1-1, Division of Reactor Licensing.
This report qualifies these motor operated v a 1 v es to 3 4 O o F
- Thermal analysis calculations were performed and the maximum surface temperature of the motor operated valve limit switch compartment was calculated to be 291°F.
These calculations were performed by Stone & Webster Engineering Corporation using the same model and technique as discussed in 8.4.8(2).
In addition, Limitorque Corporation has conducted tests illustrating that the motor operated valve and limit switch could be subjected to a temperature of 4920F for a period of 17 minutes without the surface temperature of the electrical components and motor exceeding 315oF.
M P79 5 18 13 8.4.8(3)-1 l ----- ----=,---
PSE&G concludes that Limitorque motor operated valves as supplied by Westinghouse are environmentally qualified for operation within the containment at Salem Generating Station, Units 1 and 2.
In addition, the information transmitted to the NRC by Westinghouse was part of the Westinghouse Generic Requalification Program, to which references may be found in the North Anna FSAR, Sections 3.10 and 3.11 and FSAR Supplement p3.2, p3.3, and s3.31.
North Anna and Salem utilized Limitorque Operators designated as type SMB-00, SMB-1 and SMB-3.
The SMB-2 is used by PSE&G and not North Anna.
Further specific references to the Westinghouse supplied motor operated valves for Salem Generating Station was given to the NRC in Westinghouse letter dated November 15, 1975 to Mr. D. B. vassello from Mr. c. Eicheldinger.
The North Anna environmental profile bounds the Salem pro-file and qualification of these valves has been previously accepted by the staff.
M P79 5 18 14 8.4.8(3)-2
(4) Fan Cooler Motor Preliminary information from Westinghouse indicate the Salem fan cooler motor hot spot temperature reached under accident conditions is less than the hot spot temperature the motors were previously qualified to.
Final details will be pre-pared by Westinghouse and submitted to the NRC staff for their review, upon completion.
M P79 5 18 15 8.4.8(4)