ML16341D243
| ML16341D243 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 04/15/1985 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | Shiffer J PACIFIC GAS & ELECTRIC CO. |
| References | |
| NUDOCS 8505020114 | |
| Download: ML16341D243 (12) | |
Text
4 Docket No. 50-323 APR y5 ]ggg Mr. J.
D. Shiffer, Vice President Nuclear Power Generation c/o Nuclear Power Generation, Licensing Pacific Gas and Electric Company 77 Beale Street, Room 1451 San Francisco, Cali'fornia 94106
Dear Mr:
Shiffer:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION IN REGARD TO DIABLO CANYON, UNIT 2 TECHNICAL SPECIFICATIONS As a result of our continuing evaluation of the Diablo Canyon, Unit 2 Technical Specifications, we find that additional information, identified in the enclosure, is required to complete our review.
The items in the enclosure are numbered as additions to the items in the enclosure to our letter of March 14, 1985.
Si~cerely, OQQ!NAl.SlGLED BY,'i George W. Knighton, Chief Licensing Branch No.
3 Division of Licensing
Enclosure:
As stated cc:
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Mr. J.
D. Shiffer, Yice President Nuclear Power Generation c/o Nuclear Power Generation, Licensing Pacific Gas and Electric Company 77 Beale Street, Room 1451 San Francisco, California 94106 Philip A. Crane, Jr.,
Esq.
Pacific Gas
& Electric Company Post Office Box 7442 San Francisco, California 94120 Mr. Malcolm H. Furbush Yice-President
- General Counsel Pacific Gas &"Electric 'Company Post Office Box 7442 San Francisco, California 94120
.lanice E. Kerr, Esq.
California Public Utilities Commission 350 McAllister Street San Francisco, California 94102 Mr. Frederi ck Ei ss ler, Pres ident Scenic Shoreline Preservation Conference, Inc.
4623 More Mesa Drive Santa Barbara; California 93105
's.-Elizabeth Apfelberg 1415 Cozadero San Luis Obispo, California 93401 Mr. Gordon A. Silver Ms. Sandra A. Silver 1760 Alisal Street San Luis Obispo, California 93401 Harry M. Willis, Esq.
Seymour
& Hillis 601 California Street, Suite 2100 San Francisco, California 94108 Mr. Richard Hubbard MHB Technical Associates Suite K
1725 Hamilton Avenue San.Jose, California 95125 Mr. John Marrs, Managing Editor San Luis Obis o Count Tele ram Tribune o nson venue P. 0.
Box 112 San Luis Obispo, California 93406 Diablo Canyon Resident Inspector/Diablo Canyon NPS c/o US Nuclear Regulatory Commission P. 0.
Box 369 Avila Beach, California 934?4 Ms.
Raye Fleming 1920 Mattie Road Shell Beach, California 93440 Joel
- Reynolds, Esq.
John R. Phillips, Esq.
Center for Law in the Public Interest 10951 West Pico Boulevard Third Floor Los Angeles, California 90064 Mr. Dick Blankenburg Editor
& Co-Publisher South County Publishing Company P. 0.
Box 460 Arroyo Grande, California 93420 Bruce Norton, Esq.
Norton, Burke, Berry
& French, P.C.
202 E. Osborn Road P. 0.
Box 10569 Phoenix, Arizona 85064 Mr. H.
C. Gangloff Westinghouse Electric Corporation P. 0.
Box 355 Pittsburgh, Pennsylvania 15230 David F. Fleischaker, Esq.
P. 0.
Box 1178 Oklahoma City, Oklahoma 73101
Arthur C. Gehr, Esq.
Snell 5 Wilmer 3100 Valley Center Phoenix, Arizona 85073 Mr. Lee M. Gustafson, Director Federal Agency Relations Pacific Gas 8 Electric Company 1050 17th Street, N.W.
Suite 1180 Washington, OC 20036 Regional Administrator - Region V
US Nuclear Regulatory Commission 1450 Maria Lane Suite 210 Walnut Creek, California 94596 Michael J.
Strumwasser, Esq.
Special Counsel to the Attorney General State of California 3580 Wilshire Boulevard, Suite 800 Los Angeles, California 90010 Mr. Tom Harris Sacramento Bee 21st and 0 Streets Sacramento, California 95814 Mr. H. Daniel Nix California Energy Commission 1516 9th Street, MS 18 Sacramento, California 95814 Lewis Shollenberger, Esq.
US Nuclear Regulatory Commission Region V
1450 Maria Lane Suite 210 Walnut Creek, California 94596 Mr. Thomas Devine Government Accountability Project Institute for Policy Studies l901 Que Street, NW Washington, OC 20009
7.
Table 3.8-2, Reactor Tri S stem Instrumentatio~
Res onse Times (Page 3/4-3 and Page 82-4)
In table 3.3-P, it is stated that the need to specify a response time for both the Intermediate Range and, Source Range Neutron Flux Trip is "not applicable."
Based on previous
- reviews, we understand that this is because they are claimed not to be taken credit for in safety analyses.
- However, on page B2-4, it is stated that they are relied upon.
Therefore, provide response times, consistent with the need for a power range neutron flux response time.
8.
Table 3.3-3 En ineered Safet Features Actuation S stems Instrumentation (Pages 3/4-15 to 3/4 3-17) a);
Me understand that Item 1.C, Automatic Safety Injection is required in Mode 4 on high containment pressure in order to protect the core in the event of a LOCA.
The same comnent applies to table 4.3-2, item 1.C.
b).
Item 4.a, manual steam line isolation capability should be required in Hode 4 to enable isolation of the faulted steam generato~
in case of a steam line break or a steam generator tube rupture.
9.
Section 3.4.4 Relief Valves (Page 3/4 4-10)
Me understand that Diab>o Canyon Unit 2 relies on the PORVs to be operabl~
and available in order to meet the 10 CFR 100 guideline values.
- However, the proposed technical specifications would allow them to be tajrep.out o<
c service and put in an inoperable mode.
It is unclear if the action state-ments (a) through (e) of this section ensure that a
PORV relief ath will alwa s be o erable assuming a single failure.
In particular, if a plant lost 2 PORVs, one can not be taken out of'ervice and rendered inoperable, since a single failure of a PORV would result in no pressure relief path and a violation of the FSAR assumptions for the postulated steam generator tube rupture event.
Clarify the action statements to ensure that licensing bases are met or otherwise provide a basis for a conclusion that the licensing bases will be met.
10.
Section 3/4 10.3 S ecial Test Exce tions Reactor Coolant Loo s
(Page 3/4 10-4)
This technical specification permits plant operation without any reactor coolant pumps operating up to 10$ thermal power on fission heat for startup or physics tests.
The staff is unaware of any safety analysis that demonstrates that this operating condition would be acceptable.
Provide a basis for the acceptability oF steady state operation at lOX thermal power on fission heat that includes an assessment of reactor
.coolant system temperature profiles, margins to saturation, and core DNBR.
yr:
ENCLOSURE DIABLO CANYON UNIT 2 INFORMATION REQUEST
- 6. 'able 3.3-1 Reacto~
Tr i S stem Instrumentation (Page 3/4 3-2)
Item 6.c on this table specifies that only one Source Range Monitor (SRM) channel is required to be operable during Modes 3, 4, and 5.
During these
- modes, the SRM does not provide a,reactor trip function.
However, it provides a boron dilution mitigation function by sensing the neutron flux increase and actuating alarms alerting the operator.
One ope~able SRM
~
represents a single point of vulnerability for.-the boron dilution mitigation
.system (BDMS).
During the FSAR review stage, the staff'eviewed and the BDMS on the premise that it is single failure. proof.
There<ore, this item ~eprese~ts an apparent deviation from the boron dilution analysis assumptions as approve'd by the staff.
Me note that the BDMS as reflected in the Diablo Canyon Unit 2 Technical Specigcations does not meet the single failure criterion.
Either (a) propose appropriate changes to rendering the BDMS single failure proof, or (b) provide justification for not meeting the single failure criterion.
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