ML19210E796
| ML19210E796 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 12/03/1979 |
| From: | Rubenstein L Office of Nuclear Reactor Regulation |
| To: | Parris H TENNESSEE VALLEY AUTHORITY |
| References | |
| NUDOCS 7912130001 | |
| Download: ML19210E796 (9) | |
Text
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[(pn nucoq[g UNITED STATES
- } s > ( 3 g NUCLEAR REGULATORY COMMISSION j -; j WASHINGTON, D. C. 20555
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DEC 3 1979 Docket Nos:
50-327 and 50-328 Mr. H. G. Parris Manager of Power Tennessee Valley Authority 500A Chestnut Street Tower II Chattanooga, Tennessee 37401
Dear Mr. Parris:
SUBJECT:
RE'juESTS FOR ADDITIONAL INFORMATION ON SEQUOYAH Enclosed are requests for additional information in the area of Instrumentation and Control Systems for Sequoyah.
Responses are needed by December 5,1979 to meet our schedule.
Sincerely, Li a
e-Lester S. Rubenstein, Acting Chief Light Water Reactors Branch No. 4 Division of Project Management
Enclosure:
As stated cc:
See next page 1550 011 7912130 O ()'
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Tennessee Valley Authority DEC 3 1979 CCs:
4erbert S. Sanger, Jr. Esq.
General Counsel Tennessee Valley Authority 400 Commerce Avenue EllB33 i
Knoxville, Tennessee 37902 2
1 Mr. E. G. Beasley y'
Tennessee Valley Authority 400 Commerce Avenue
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Knoxville, Tennessee 37902
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Mr. Michael Harding es Westinghouse Electric Corporation i
P. 0. Box 355 Pittsburgh, Pennsylvania 15230
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Mr. David Lambert
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Tennessee Valley Authority 400 Chestnut Street Tower II Chattanooga, Tennessee 37401 4
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1 a-ADDITIONAL INFORftATION NEEDED TO RESOLVE SEQUOYAH SER OPEN ITEMS 1.
Seismic Qualification of Westinchouse Supolied Class IE Ecuicment We found the response to Question 7.60, particularly Table Q7.63-1 unaccepu bk as follows:
1.
Specify the lot nurrber for the Barton 763 and 764 Transmitters.
2.
You state in. Table Q7.60-1 that the qualification of ASCO soleroid valves is given in a letter to Westinghouse PWR-SD.
Provide for our review a copy of this letter. Should it not contain information on monitoring of the equipments operation during and after the test and the test results, you must provide this information.
3.
The Safeguards Actuation Racks were omitted from the table. Provide information in the table showing their seismic qualification or justify and provide bases for not providing this information.
4.
Provide more complete identification cf the Safeguards Tes: Cabinet.
State if it is the model described in Westinghouse referenca crawing number 1054E95.
If not, provide the drawing number and. complete information on its seismic qualification testing.
5.
Verify, by note or otherwise, in the table tha the Lir.it..rque valve motor operators supplied by Westinghouse are the same as '. ase supplied by TVA.
If they differ, identify the differences and she that the differences de not affect the seismic cualification.
Also revise note b to reference the latest seismic test reports (Lockheed 2521-4511 dated June 17, 1974 and Aero Nav 5720 dated January 6,1975) furnished for our eval ua tion.
6.
Identify the pump motors (Centrifugai Charcing, Safety injection, er.d-Residual Heat Removal) and for each motor type provide a copy of the seismic qualification report for our review.
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The Containment Spray pump mo. tors were omitted frc= the table.
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Identify them and furnish for our review a copy of the seismic qualification report for these motors.
i II. Environmental Qualification of Westinchouse Sucolied Class IE Eouioment Your response to Question 7.60, particularly Table Q7.50-1 was incomplete in these respects.
1.
The information contained in NS-CE-755 did not address the qualification j
of the ASCO E300 series solenoid valves for use inside the containment.
We require that:
(a) a test report showing these valves to be qualified for service in the worst case environment in the containment be provided for review, and (b) these five itens from I&E Bulletin 79-01A be complied with for al?"*4:
solenoid valves used in safety-related applications inside tne containment.
(1)
The parts of the solenoid valve made of acetal plastic material ruuid be replaced with similar parts mace of metal which can be pravided by ASCO.
(2)
The valve seals and gaskets which are made of Buna "N" material should be replaced with viton elastomers, cor.sidered by ASCO as suitable for the service intanded.
(3)
Review and determine that the coils of the solenoid. valves installed inside containment are Class "HT" or "HB" as reau for high temperat
'nvi ronmental conditions.
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inside containment have at least a NEMA 4 enclosure rating.
(5) Establish a preventive maintenance program to assure replacement of those valve parts identified above in the time period recomrended in the appropriate ASCO valve bulletin.
The acceptable alternative to the above program is to replace all the unqualified valves used in safety-related applications inside the containnent with qualified valves, provide a copy of the environmental qualification report, and institute an appropriate preventive maintenance program similar to that identified by (b5) above. provide a response showing how the requirements of this position will be met.
2.
Foxboro E13DH differential pressure transmitters are located inside the containnent to provide the low coolant flow trip. Provide information showing that these transmitters are environmentally qualified to confer-to our position that safety-related equipment shall remain functional in the accident environment for a period of at least one hour in excess of the tine assumed fer its operation in the accident analysis.
3.
The Safecuards Actuation Rack, Containment Air Re urn Fans, anc Cm..iin=c-Sprey Fump motor were omitted from Table Q7.60-1. Also the following listed ecuipment, located outside the containment, did not has'e any docuTentation listed in the table that presents the environmental specifications and shows that the equipment meets them.
This equipment includes: (a) Foxboro E11 GM pressure transmitters, (b) Foxboro E U D"r differential pressure transmitters, (c) Hydrogen Recombiner control
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(g) Reactor Trip Switchgear, (h) Safeguards Test Cabinet, (i) Valve Motor Operators, (j) ASCO solenoid valves, and (k) the
_ Centrifugal Charging, Safety Injection and Residual Heat Re oval pump motors.
Revise the table to provide references to documentation -
that shows the qualification of this equipment to survive and operate in its worst case environment.
III.
Table 3.11-2 Concerns Table 3.11-2 is incomplete and certain portions are unacceptable. The followino additional information is required for us to complete our revi_ew.
1.
In several places in Columns.7 and 8 of Table 3.11-2 the entry "NA" is given. This entry is unacceptable since the r.ormal operation radiation dose rate and total integrated normal cperation dose applies and should be given for each of the non-accident conditions.
Revise the table to include these values.
2.
For the entries in Column 9 of taw 3.11-2 identify 'the tire period over which the dose is integrates
- t is not clear from the table if the integrated cccident dose ir.cli. a the " normal operation" integrated 40 year dose in addition to the i: :; rated dose resulting only from the pos tulated accident.
In some can:. the " normal operation" integrated 40 year dose amounts to as much as 50 percent of the indicated accident dose.
Therefore, if the integratec accicent dose does not include this
" normal operation" 40 year dose you must justify that the equipment is qualified to function in the acciaer.t environment.- Revise Table 3.11 address this concern and revise FSA?. Section 3.11 to clarify and justify your response.
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3.
Table 3.11-2 does not censider the effects of a steamline or feedwater line break occurring in the Auxiliary Building near the penetrations or in the vicinity of the Auxiliary Building ventilation air intake which is located ininediately above both the four main steamlines and the four main feedwater lines for each unit. Revise Table 3.11-2 to include consideration of these occurrences for safety-related equipment located in these areas. Table Q7.60-1 should also be revised to ensure that these occurrences have been considered in the reference to qualification documentatice for safety-related equipment located in these areas.
IV. Table 3.11-3 Concerns Table 3.11.3 is incomplete and portions of it remin unacceptable.
The following additional information is required for us to complete our review.
1.
On hge 3.11-6 the listing of components for the Reactor Protection Systen contains these omissions:
(a) containment pressure, (b) low head flow, (c) accumulator level, (d) steam generator level, and (e) UHI accumulator level instrumentation.
Revise the table to include these parmeters or justify their omission.
7 2.
On Page 3.11-6 the total radiation dose of 2.1 x 10 Rads appears c.o be that listed in Table 3.ll-2^for the 40 year normal operation dose.
Provide the basis for this number and revise the column headed " comments" for the Reactor Protection System entry to show that this safety-related equipment will remain functional in the accident environment for a pericj of at least one hour in excess of the time assumed for its operation in the accident analysis.
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On Page 3.11-6a for the Containment Spray System, the pipi$g, heat exchangers, valves, and pump and motor are all lqcated in Auxiliary 0
0 Building cooled rooms but three different values (1150, 150, 104 )
of temperature are given.
Provide'the basis for these values. Also the spray header and nozzles are in the upper compartment of the 0
containment and have a design temperature of 190 F.
The Containment Air Return Fan is also located in the sama upper compartment but its 0
rating is 250 F.
Provide the basis for'these values.
4.
On Page 3.11-7 for each of the total radiation dose entries provide the bases on which this total dose was cocputed.
5.
On Page 3.11-7 for the Containment Isolation System entries further identify the containment location as either upper or lower compartment.
If the equipment item is used in both compartments, confirm that the N'
design conditions enveloce the most severe service conditions.
6.
On Page 3.11-7, for the airlocks and equipment hatch entries:
(a) Explai:
why a 700 peak design temperature is used for the airlocks, but only U
a 220 F peak design temperature is.se; for the equipment hatch.
(b) Your inclusion of only the airloc.;
.r.d equipment hatch appears inadequate since our requirements are t ::: the containment retain its integrity for at least 30 days after the accident. Revise this entry to consider the need for a higher racittien qualification dose that shouic include the 30 day accident dose in 2ddition to the accident and " normal" 40 year doses.
7.
On Pages 3.11-7, 8, 9 for those entries wnere the symbol "c" is used in tr
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" peak de:ign temperature" and " peak design humidity" columns provide the values of these parameters that are used in the equipment specifications.
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On Page 3.11-9 specify the value to which the humidity is regulated for those entries where the symbol "d" appears.
9.
On Page 3.11-9a for the equipment i'n the Auxiliary Feedwater System furnish the expected dose rate and total dose. For the instrumentation and controls located inside the containment state whether they are located in the upper or lower compartment.
State also if the specified total radiation dose contains the " normal" 40 year dose as well as the postulated accident dose.
For those instruments used for post-accident monitoring the specified dose should contain the post-accident period dose.
Justify any exceptions to these recommendations.
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