ML20151H476
| ML20151H476 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 07/19/1988 |
| From: | Kalman G Office of Nuclear Reactor Regulation |
| To: | Firlit J SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| References | |
| NUDOCS 8808010299 | |
| Download: ML20151H476 (4) | |
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NUCLE AR REGULATORY COMMISSION
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Juiy 19, 1988 t.,
f Docket No. 50-312 l
i ler, Jce Firlit Chief Executive Office Nuclear Rancho Seco huclear Generating Station l
l 14440 fwin Cities Road I
Herald, California 95E38-9799
Dear Mr. Firlit:
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SUBJECT:
NRC EVALUATION OF BWOG GENERIC rep 0RT "DES!GN REQUIREMENTS FOR i
055 AND AMSAC" i
i Tre purpose of this letter is to provide the staff's evaluaticn of B&W Document 47-115909100, "Design Requirements for Diverse $ cram System (055) and ATWS Mitigation System Actuation Circuitry (AMSAC)," prepared by Babcock and Wilcox for the Babcock and Wilcox Owners Group (BWOG) ATWS Comittee. This BWOG generic report was submitted by letter dated October 9 1985 (from J. Ted Enos, Chatrnan BWOG ATW5 Comittee to Hugh L. Thompson, NRC), pursuant to requirerents specified in the Code of Federal Regulation (CFR), Section 10 CFR 50.62, "Requirements for Reduction of Risk from ATWS Events for Light-Water Cooled Nuclear pcwer Plants."
l The BWCG generic report provides the generic design basis for ATWS rodifications of C&W type nuclear power plants required by 10 CFR 50.62.
Subsecuent to the r
generic report sabotttal, the staff met with members of the BWOG ATWS Standirg l
Comittee, on October 28, 1987 to discuss potential open items which were raised during the staff review of the generic report. Following this reeting, the BWOG subnitted another set of responses to the remaining open iters b dated December 1, 1987 from J. Ted Enos (BWOG) to Frank J. Miraglia (y letter l
hRC).
t Based on our review of the information provided in the BWOG generic report and t
the supplerental letter of December 1,1987 the staff concludes that most I
sectionsofthegenericreportareacceptableforprovidinggenericguicelines for plant specific design submittals. However, some areas of the generic design I
are still of concern to the staff. Therefore, the staff has presented several design requirements in the attached safety evaluation report (SER) which should be followed by the utilities when censidering their plant specific OSS and j
AFSAC designs.
Followin tutcittals swst address:g are the areas of concern that plant-specific r
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The BWOG generic report is not acceptable where addressing the i
use of pcwer supplies for 055 and AMSAC.
In this regard, the i
staff suggests that special attention be given to tho acceptable rethods as presented in Section 5.6 of the SER.
The use of qualified isolation devices should also be addressed in detail in the plant specific submittals. Whether otverse or g
existing isolators are used, the staff suggests that the utilities l
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use Section 5.1 and 5.2 of the SER for guicance when addressing this istue in their $ctnittals, l
The plant specific submittals must provice detailed infortiation j
which describe how a total loss of fetcwater ficw will be detected I
j 400 why the reasurerrents chosen are irdicative cf a total less of i
feedwater ficw.
Section 6.5 of the SER provides additional guidance that the plant specific submittal should consider when addressing l
l the input parameters which have been chosen to initiate 055 and/or i
Other areas of concern to the staf f include:
(1)bypassesand I
displays, and (2) survetilance and testing. Specific guidance for j
j plant-specific submittals are presented in Sections 5.9 through
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5.12 and 5.14 for "Bypasses and Displays" and Section 6.4 for "Surveillance and Testing" of the SER.
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Design details such a physical and operational characteristics of those 055 l
and AMSAC components which are not addressed in either the BWOG generic report 1
or the plant-specific submittals and may influence the staff's conclusions concerning compliance to requirements of the ATWS 50.62 "rule" will be reviewed and inspected on a plant-specific basis.
1 In sumary, the staff requests that licensees of B&W designed nuclear power plants who are part of the EWOG and are comitted to the requirerents specified i
in the ATWS E0.62 "rule" provide plant-specific submittals which address these requirements and schedules for installation of the equipment no later than 90
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working days free the date of receipt of this safety Evaluation Repor*,. With i
this acceptance of the proposed generic design, we would now expect each j
licensee to proceed wit 4 irplementation of the ATWS codifications.
1 Should you have any questions concerning the ratters discussed above or the content of the attached $ER, please contact Vincent Tronas of our staff on (301) 492 0786.
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Sincerely, i
- N George Ka
, Project Manager j
Froject Directorate V i
j Division of Reactor Frojects - !!!,
j lY, Y and Special Projects l
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Enclosure:
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As stated i
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July 19,1988 use Section 5.1 and 5.2 of the SER for guidance when addressir.g this issue in their subnittals.
The plant-specific submittals must provide detailed inforration whici describe how a total loss of feedwater flow will be detected and why the r.easurements chosen are indicative of a total loss of l
feedwater flow.
Secticn 6.5 of the SER provides additional guidance that the plant-specific submitt:1 shouid consider when addressing the input paranaters which Fave been chosen to initiate DSS and/or i
j AMSAC.
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Other areas of concern to the staff include:
(1) bypasses and i
displays, and (2) surveillance and testing.
Specific guidance for plant-specific submittals are presented in Sections 5.9 thrcugh 5.12 ard 5.14 for 'Eypasses and Otsplays" and Section f.4 for "Surveillance and Testing" of the SER.
Design details such a physical and operational characteristics of those DS$
i and AMSAC components witch are not addressed in either the BWOG generic report I
or the plant-specific submittals and may influence the staff's conclusions l
concerning corpliance to requirerents of the ATWS 50.62 "rule" will be reviewed l
and ins cted on a plant-specific basis.
j In sumary, the staff requests that licensees of E4W designed nuclear power plants who are part of the EWOG and are comitted to the requirements specified f
in the ATW5 50./.2 "rule" provide plant-specific sutmittals which address these requirenents and schedules for installation of the equiprent to later than 90 working days from the date of receipt of this Safety Evaluation Report. With this acceptance of the proposed generic design, we would ocw expect each licensee to proceed with irplementatien of the ATW$ sodifications.
Should you have any questions concerning the ratters discussed above or the centent of the attacted SER, please contact Vincent Thoras of our staff on (301) 492 0786.
Sincerely, original signed by 1
George Kalcan, Project Manager froject Directorate Y l
Division of Reactor Frejects - !!!,
IV, Y and Special Projects
Enclosure:
DISTRIEUTION As stated
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Kr. Joe Fir 11t Pancho Seco huelear Gcrerating Chief Executive Officer. Nuclear Staticn Sacrarento Municipal Utility District i
14440 Twin Cities Road Herald. California 95638-9799 l
5 i
cC' Mr. David S. Kaplan. Secretary Mr. John Bartus
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end Gential Counsel Ms. JoAnne Scott I
Sacramento Municipal Utility Federal Energy Regulatory Corsnission i
District 825 North Capitol Street. N. E.
6201 $ Street Washington. 0.C.
20426 l
P. O. Box 15830 Sacramento California 95813 Mr. Barclay S. Lew Pacific Gas and Electric Corpany Thocas A. Baxter. Esq.
77 N. R Street (333/A613) j Shaw. Pittman. Fetts & Trowbridge Sa-W isco, CA 94106 i
2300 N Street. N.W.
Washington. 0.C.
20037 Ms i s en Hubbard P. O. Box 63 Mr. Steven Crunk Sunol. California 94586 Manager, Nuclear Licensing Sacrarento Municipal Utility District Rancho Seco Nuclear Generating Station 14440 Twin Cities Road Herald. California 95638 9799 i
Mr. Robert C. Borsum Licensing Representative i
Babcock & Wilcox I
Nuclear Power Division 1700 Rockville Pike - Suite 525 Rockville. Maryland 20052 Resident Inspector / Rancho Seco j
c/n U. S. N. R. C.
I 14440 Twin Cities Road Herald. California 95638 j
Regional Administrator Region Y f
U.S. Nuclear Regulatory Coassission l
1450 Maria Lane. Suite 210 Walnut Creek. California 94596 Mr. Jack McGurk. Acting Chief Radiological Health tranch t
State Department of Health Services l
714 P Street. Office Butiding #8 Sacramento California 95814 Sacramento County Board of Supervisors 700 H Street. Suite 2450 Sacramento. California 95814
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