ML19257A442
| ML19257A442 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 12/17/1979 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | Hancock J FLORIDA POWER CORP. |
| References | |
| IEB-79-05C, IEB-79-5C, NUDOCS 8001040299 | |
| Download: ML19257A442 (5) | |
Text
-
/
'o UNITED STATES E'
N NUCLEAR REGULATORY COMMISSION E
WASMNGTON. D. C. 20555 71
]
g
'+A
~
December 17, 1979 Docket No. 50-302 Mr. J. A. Hancock Director, Nuclear Operations Florida Power Corporation P. O. Box 14042, Mail Stop C-4 l
St. Petersburg, F1orida 33733
Dear Mr. Hancock:
SUBJECT:
AUTOMATIC REACTOR COOLANT PUMP TRIP DURING SMALL BREAK LOSS-0F-COOLANT ACCIDENTS (LOCA)
The long-tenn requirement of IE Bulletin 79-05C requires the B&W licensees to submit a design which will assure autcmatic tripping of the operating reactor coolant pumps (RCPs) under all. circumstances in which this action may be needed.
It has been shown through analysis that this trip is needed for a certain spectram of small break LOCAs.
In order to assure that the operating RCPs are tripped during LOCA conditions yet minimize the pcssi-bility of tripping the RCPs during non-LOCA transients (such as severe overcooling events), the B&W licensees have proposed a conceptual safety-grade trip circuit which would utilize coincident input signals of low pressure ESFAS actuation combined with icw RCP current / power.
The use of these coincident signals was discussed in detail during a meeting held in Bethesda, Mar / and on November 8,1979, between the staff, the B&W l
Owners' Group and B&W. The staff expressed two concerns with the proposed design.
First, while the staff agrees that a decrease in RCP current / power will occur if voiding takes place in the reactor coolant system, the relationship of RCP current / power versus void fraction has neither been fully documented by the licensees nor demonstrated through full scale testing.
Secondly, absent the above infomation, the staff is not convinced that the proposed setpoint of 20f. decrease in RCP current is the proper setpoint for jhat portion of the coincidence logic.
Although these matters must be resolved as part of the final design acceptance, we believe that the proposed design contains sufficient flexibility and can be expected to meet its intended function.
Therefore, the B&W licensees shcule preceed with equicr:ent procurement and development of a final design based on the preposed concept.
1684 IM 80 01040 2 f
.. Prior to final design acceptability, the following conditions must be satisfied:
1.
Characteristic curves for RCP current / power versus void fraction cust be fully demonstrated and documented based upon existing ~ test data and supplemented as necessmy with confimaton data obtained from future tests such as LOFT, full scale testing, etc.;
2.
Justification for the RCP current / power setpoint nust be shown; and, 3.
Satisfactory responses to the enclosed request for additional infonnation must be received.
It is requested that within 30 days of receipt of this letter, licensees shall provide a schedule for responding to items 1 through 3 above.
In addition, a prcposed schedule for installing the automatic RCP trip circuitry shall also be
- p rovided. Your installation schedule should include the expected reactor down time associated with the final hookup and testing of this circuitry.
If any additional infomation is needed, please contact your NRR Operating Reactor Project Manager, Mr. Morton B. Fairtile on (301) 492-7435.
Sincerely,
/ /)/f.
~
g Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Enclosure:
3euest for Additional Infomation - Automatic RCP Trip cc w/ enclosure:
,See next page 1684 139
' Florida Power Corporation 1
nr. S. A. Brandimore Mr. Robert B. Borsum Vice President and General Counsel Babcock & Wilcox P. O. Box 14042 Nuclear Power Generation Civision St. Petersburg, Florida 33733 Suite 420, 7735 Old Georgetov.n Road Bethesda, "aryland 20014 Mr. Wilbur Langely, Chairman Board of County Commissioners Citrus County Iverness, Florida 36250 Bureau of Intergovernmental Relations U. S. Environmental Protection Agency 660 Apalachee Parkway Region IV Office Tallahassee, Florida 3230c ATTN:
EIS C0CRDINATCR 345 Courtland Street, N.E.
Atlanta, Georgia 30308 Director, Technical Assessment h
D Division j
Office of Radiation Programs
( A'a'-4 59 )
U. 5. Environmental Protection Agency Crystal Mall #2 Arlington, Virginia 20460
'Mr, J, Shreve The Public Counsel Room ? Holland Bldg, Tallahassee, Florica 32304 Mainistrator Department of Environmental Regulation Power Plant Siting Section State of Florida
, Montgomery Building 2552 Executive Center Circle, E.
Tallahassee, Florida 32301 At :rney General
- s:s-: en
- Lecal A##ai-s Pe :a:itol Til'a assee, :lorida 323:'
1684 140
Enclosure s
ADDITIONAL INFORMATION REOUIRED FOR AUTOMATIC TRIP CIRCUITRY FOR THE REAC OR COOLANT PUP? MOTORS n
We have reviewed the preliminary design descriptions of the automatic trip circuitry for the subject motors which have.been provided by the B&W plant licensees. Since it has been concluded that this action is required to perform a safety function, the added circuitry should conform to specified safety criteria.
When submitting the proposed final design for the autcmatic trip circuitry, provide responses to the following questions:
1.
For your proposed design, state the degree of confonnance with the applicable acceptance criteria listed in Column 7.2 of Table 7-1 of the Standard Review plan. Also, provide justification for any non-conformance.
2.
Provide a discussion of the following:
confonnance of the design with the# design requirements of Section 4 a.
of IEEE Std._279-19711 and, b.
confonnance of the design with the principal design criteria of Section 4 of IEEE Std. 308-1974.
3.
Provide a detailed description of any changes to and/or interfaces with the existing protection systems. Include diagrams (block, location, functional, and/or elementary wiring), as necessary, to clearly depict the changes and/or interfaces.
In addition, provide an analysis which demonstrates that these changes and/or in erfaces will not degrade the existing ?rotection sysca.s.
4.
Identify equipment whicn is identical to ecuipmen: utili:ed in existing safety-grade systems.
For the equipment whicn is not identical, briefly describe the differences.
5.* In general, the equipment shall be seismically and envircrrnentally qualified.
Therefore, provide the following descriptive infonnation for the qualification test programs:
equipment design specificaticn requirements; a.
b.
test plan; c.
tes setup; es :rocecures; a :,
s.
3::e::abili y g:als 5 : re:.- e en s.
1684 141 i
ADDITIONAL INFORMATION HECUIRFD FCR AUT0!w!!! TRIP CIRCUITRY FOR THE REA~~
COOLANT ?'.9.'OTC?.5 (CO'.T;';L'ID)
When submitting your final design fc-app-:vsl, if all of the above information is not available, provide a sc.edule for its submittal.
6.' Provide the criteria for the overall trip circuitry installation testing which will demonstrate that this circuitry has been installed properly.
When submitting your final design for approvsi, if this information is not available, provide a schedule for its subtittal..
Nh2d
~
1684 142
.