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Category:ARCHIVE RECORDS
MONTHYEARIA-87-758, Requests for Addl Info Re Review of Responses to Action Item E of IE Bulletin 85-0031987-11-16016 November 1987 Requests for Addl Info Re Review of Responses to Action Item E of IE Bulletin 85-003 ML20236P8911987-11-16016 November 1987 Requests for Addl Info Re Review of Responses to Action Item E of IE Bulletin 85-003 ML20235Q8511987-09-14014 September 1987 Rev 1 to 32-1167603-01, Pressurizer Shell Temp Due to Radiant Heat ML20235Q7981987-09-14014 September 1987 Rev 1 to 32-1167974-01, Local Heating of Pressurizer Shell Inside Corner ML20235Q9641987-08-14014 August 1987 Audit Rept 87-020 on 870814 Re Station Mods ML20151M9601987-07-20020 July 1987 Package of NRC Administered Requalification Exam Results Summary ML20197A5291986-10-17017 October 1986 Package of Nuclear Insurance Info,Including Endorsements & Amends to Insurance Policies ML20214L5431986-03-10010 March 1986 Viewgraphs Entitled, Smud ML20214L5521986-01-20020 January 1986 Package of Two Documents Entitled, Action List,851226 Transient ML20138Q9341985-11-14014 November 1985 QA Audit Rept 0-745 on 851001-11 Re Meteorological Program. Open Items Include Need for Backup Data Retrieval Sys Relying on modem-based Access to Meteorological Data Base & Incomplete Acceptance Testing of Midas Sys ML20129F4831985-05-0909 May 1985 Package of Compilations of Results of Operator Licensing & Requalification Exams ML20126L2391981-05-0101 May 1981 Viewgraphs Entitled Westinghouse PWR Vessel Integrity & Consideration of Rancho Seco Occurrence (3/78) ML19322C7631978-06-30030 June 1978 Press Release Discussing 780320 Loss of Nonnuclear Instrumentation of Rancho Seco & Jan 1978 Diesel Generator Trip at DC Cook 2 ML19308C0241978-06-19019 June 1978 Transient Committee Rept on 780320 Transient at Rancho Seco. Total Nonnuclear Instrumentation Y Power Supply Loss Caused by Inoperable Fuse.New Procedures Written for Loss of NNI-X & NNI-Y Power ML19317G9571970-08-21021 August 1970 News Articles Published by Sacramento Bee Re Facility ML19319E2781969-03-0606 March 1969 Press Release Re Topics Discussed at Util 690306 Board Meeting ML19317G9621968-09-19019 September 1968 News Articles Published by Sacramento Union Re ASLB 080917-18 Public Hearing on Proposed Facility Const 1987-09-14
[Table view] Category:PACKAGE OF NONCODED MATERIAL
MONTHYEARIA-87-758, Requests for Addl Info Re Review of Responses to Action Item E of IE Bulletin 85-0031987-11-16016 November 1987 Requests for Addl Info Re Review of Responses to Action Item E of IE Bulletin 85-003 ML20236P8911987-11-16016 November 1987 Requests for Addl Info Re Review of Responses to Action Item E of IE Bulletin 85-003 ML20151M9601987-07-20020 July 1987 Package of NRC Administered Requalification Exam Results Summary ML20197A5291986-10-17017 October 1986 Package of Nuclear Insurance Info,Including Endorsements & Amends to Insurance Policies ML20214L5521986-01-20020 January 1986 Package of Two Documents Entitled, Action List,851226 Transient ML20129F4831985-05-0909 May 1985 Package of Compilations of Results of Operator Licensing & Requalification Exams 1987-07-20
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1 REQUEST FOR ADDITIONAL INFORMATION (RAI) RE:
Review of Responses to Action Item e-of IE Rulletin 85-03 Licensee:
Unit (s): Rancho Seco'1 I
Sacramento Municipal Utility Date of-' Response: 05-16-86' District 05-86 6201 S Street 11-05-86 P. O. Box 15830 Respondent:
Sacramento, CA 95813 J..E. Ward.
l Assistant General Manager, Nuclear The information provided in your response to Action Item e of IE Bu11etin 85.03 was found to be deficient in some. areas. Please provide the additional infor--
i mation necessary to resolve. the following comments and questions:
1.
Unidentified MOVs in discharge ifnes of the core flooding tank _ safety-injection system are shown normally open on FSAR figures 6.1-1 and 6.' 2-1, both Amendment 2.
The possible problem that the system would be inoperable if the MOVs were left closed inadvertently should be addressed. Based'on l
the assumption of inadvertent equipment operations as required by. Action Item a of the bulletin, revise Table 1 of the response of May 16,'1986 to 1
include these two valves.
a 2.
Differential pressures for AFW discharge MOVs 20577 and 20578 and cross-connect MOVs 31826 and 31827 have been compared with those listed for equivalent valves at two other B&W plants. This comparison. indicates i
that the delta-Ps for Rancho Seco 1 should be~ about l.38 times greater for i
opening and closing.
Please justify or correct this apparent discrepancy.
3.
Has water hammer due to valve closure been considered in the determination -
of pressure differentials? If not, please explain..
s 4
According to the response of 11-05-86, the method proposed for. setting switches involves counting handwheel turns. This method is not recom-mended, because of one of the problems at Davis-Besse 1 reported in IER 85-03. Please provide a description of.how the problems at Davis-Besse 1 caused.by counting handwheel turns will be' compensated for at your facility.
8711190056 871116 PDR FOIA GR ABER B7-758 PDR A \\
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