ML20113A666
| ML20113A666 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 01/15/1985 |
| From: | Mittl R Public Service Enterprise Group |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8501210179 | |
| Download: ML20113A666 (20) | |
Text
m Pubhc Seruce g
Electnc and Gas Company 80 Park Plaza, Newark, NJ 07101/ 201430-821)
MAILING ADDRESS / P.O. Box 570, Newark, NJ 07101 Robert L Mitti General Manager Nuclear Assurance and Regulation January 15, 1985 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20814 Attention:
Mr. Albert Schwencer, Chief Licensing Branch 2 Division of Licensing Gentlemen:
HOPE CREEK GENERATING STATION DOCKET NO. 50-354 FSAR COMMITMENT STATUS THROUGH DECEMBER 1984 Public Service Electric and Gas Company plans to issue Amendment No. 9 to the Hope Creek Generating Station ~ Final Safety Analysis Report by February 15, 1985.
This letter is provided to document the status of Hope Creek Generating Station responses to NRC requests for additional information which were forecasted to be responded to by December 1984.
Attachment I is a tabulation of the Hope Creek Generating Station Final Safety Analysis Report commitments for December 1984, and the corresponding resolution for each commitment.
Attachments II through VIII provide responses to commitments forecasted to be responded to in December 1984, which will be included in Amendment No. 9 or 10.
i I 8501210179 850115 DR ADOCK 05000354 PDR The Energy People
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.q, Director of Nuclear Reactor Regulation 2
1/15/85 Should you have any questions in this regard, please contact us.
Very truly yours,
/
Sg Attachment I
- Hope Creek Generating Station - FSAR Commitment Status through December 1984 Attachment II
- Response to FSAR Table 13.1-4 Attachment III
- Response to TMI Item II.K.3.30 Attachment IV
- Response to Question 210.1 Attachment V
- Response to Question 210.2 Attachment VI
- Response to Question 210.21 Attachment VII
- Response to Question 480.4 Attachment v. ;I - Response to Question 430.33 1
D.JH. Wagner (w/ attach)
USNRC Licensing Project Manager A.~R.
Blough (w/ attach)
USNRC Senior Resident Inspector
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ATTACHMENT I HOPE CREEK GENERATING STATION FS AR COMMITMENT STATUS THROUGH DECEMBER 1984 FSAR Commitment Location Commitment Resolution
'l.
FSAR Table 13.1-4 This commitment concerns providing resumes for Senior Radiation Protection Supervisor and Senior Radiation Engineer.
This information will be provided in June 1985.
This revised
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commitment date, provided in Attachment II, will be included in Amendment 9 to the HCGS FSAR.
2.
Question / Response Re:
TMI Item I.D.1; This commitment Appendix:
concerns providing a detailed control Question 100.6 room review to verify human factors considerations.
This information has been provided in letter; R.
L. Mittl (PSE&G) to A. Schwencer (NRC), dated August 14, 1984.
Re:
TMI Item II.K.3.27; This commitment concerns establishing a common reference point for instruments measuring water level in the reactor vessel.
This information will be _ provided in January 1985.
Re:
TMI Item II.K.3.30; This commitment concerns resolving any NRC concerns with the GE small-break-model-prior to the initiation of the HCGS - specific ECCS analysis. ' Resolution has been provided by GE as stated in the HCGS SER, Section-15.9.3 (II.K.3.30).
The information deleted in Attachment III will be deleted in Amendment 9 to the HCGS FSAR.
3.
Question / Response This commitment concerns.providing Appendix:
revised FSAR ?igure 3.6-34 to reflect the Question 210.1 final stress report data.. This_informa-tion will be provided in April 1985.
This revised commitment date, provided in Attachment IV, will be included in Amendment 10 to the HCGS FSAR.
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2 FSAR Commitment Location Canmitment Resolution 4.
.0uestion/ Response This commitment concerns providing Appendix:
information labelled "later" in FSAR Ouestion 210.2 Tables 3.9-5d, Sg, and 5s.
This informa-tion will be provided June 1985.
This revised commitment date, provided in Attachment V, will be included in Amendment 9 to the HCGS FSAR.
5.
Question / Response This commitment concerns providing Appendix:
revised FSAR tables and figures in Question 210.21 Section 3.6 to reflect the final stress report data.
This information will be provided April 1985.
This revised commitment date, provided in Attachment VI, will be included in Amendment 10 to the HCGS FSAR.
6.
Question / Response This commitment concerns providing Appendix:
revised FSAR tables and figures in Question 210.24 Section 3.6 to reflect _the final stress
-report data.
This information will be provided in April 1985.
7.
Question / Response This commitment concerns providing an Appendix:
analysis of power t'o vital instruments -
-Ouestion 421.42 and controls.
This information has boon provided in Amendment 8 to the HCGS FSAR.
8.
Question / Response
. This commitment concerns.providing an
. Appendix:
analysis:of power and sensing line Question 4 21.51 failures.
This information has been-provided in Amendment.8 to the HCGS FSAR.
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9.
Question / Response Tbis commitment concerns providing~and Appendix:
analysis of a HELB on non-safety Question 421.52 controls.
This information has been provided in Amendment 8 to the HCGS FSAR.
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FSAR. Commitment
-Location Commitment Resolution
-10. Question / Response This commitment concerns providing Appendix:
information regarding modifications to Question 480.4 vacuum breakers on Mark I containments in compliance with NRC, Generic Ler.ter 83-08.
This information has been provided in the response to Ite.s 4 submitted in letter, R. L. Mitt. (PSE&G) to A. Schwencer (NRC), dated Jar uary 7, 1985.
The information provided in Attachment VII which references this response will be included in Amendment 10 to the HCGS FSAR.
J11. Ouestion/ Response This commitment concerns providing the Appendix:
results of testing an inverter as isola-Question 430.33 tion device.
( Re f:
DSER OI No. 259)
This information will be provided in February 1985.
This revised commitment date, provided in. Attachment VIII, will be ' included in Amendment 10 to the HCGS FSAR.
- 12. DSER Open Item This commitment concerns providing No. 262 Radiological Effluent Technical Specifications (RETS).
This information will be provided in February 1985.
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1 TABLE 13.1-4 (cont)
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SENIOR RADIATION PROTECTION SUPERVISOR l
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TABLE 13.1-4 (cont)
Page 90 of 93 l
SENIOR RADIOLOGICAL ENGINEER l
Will be provided by Me:7i=r l o n* _
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i-HCGS FSAR 10/84 performing the necessary work and submitted this information for staff review and approval.
Response
hoi' General Electric provided information concerning the NRC's small-break-model concerns in a meeting between GE and the NRC staff held on June 18, 1981 and subsequent documentation included in a letter from R.H. Bucholz (GE) to D.G. Eisenhut (NRC) dated June 26, 1981.
Based on its review of this information, the NRC 4
staff has prepared a draft safety evaluation report (SER) that concludes the test data, comparisons, and other information submitted by GE acceptably demonstrate that the existing GE small-break model is in compliance with 10 CFR 50, Appendix K-and, therefore, no model changes are required. -Shvold the "KC -
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i II.K.3.31 PLANT-SPECIFIC CALCULATIONS TO SHOW COMPLIANCE i
WITH 10 CFR 50.46 l
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Plant-specific calculations using NRC-approved models for small-break loss-of-coolant accidents as described in II.K.3 item 30 to
- show compliance with 10 CFR 50.46 should be submitted for NRC approval by all licensees.
l Calculations to be submitted by January 1, 1983 or 1 year after staff approval of loss-of-coolant accident analysis models, whichever is later (required only if model changes have been made).
Response
j Small-break LOCA calculations are described in Section 6.3.3.7,
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and the results are summarized in Table 6.3-4.
The references in Section 6.3.6 describe the currently approved Appendix K methodology used.
Compliance with 10 CFR 50.46 has been previously ptablished by the NRC.
No model changes are necessary (see response to item II.K.3.30),
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HCGS FSAR 10/84 QUESTION 210.1 (SECTION 3.6)
Provide the date that the many tables and figures identified as "later" will be submitted.
RESPONSE
The following tables and figures are identified as later and will be provided according to the schedule indicated below l
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-- 8/83 OUESTION 210.2 (SECTION 3.9)
Provide the data that the information identified as "later" in Tables 3.9-5d, 3.9-5g and 3.9-5s will be submitted.
RESPONSE
The allowable forces and moments on the equipment nozzle The actual values will be available in Junt nB6-ne:nection will be met.--rrr :::
after the piping as-built analysis / reconciliation con effort is completed.
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OUESTION 210.21 (SECTION 3.6.2)
In order to assure the pipe break criteria have been properly implemented, the Standard Review Flan requires the review of sketches showing-the postulated rupture locations and of summaries of the data developed to select postulated break locations including, for each point, the calculated stress intensity, the calculated cumulative usage factor, and the calculated primary plus secondary stress range.
The required sketches and tables have not been provided at this time.
Provide a schedule for submission of these data.
RESPONSE
i Figures and tables of Section 3.6 pertaining to the development and selection of pipe break locations have been revised to incorporate the preliminary stress information.
Based upon the final stress reports, the above noted sketches and tables will be updated to final status by 0:::.tcr 1904.
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DEC 31 '840 'd?610 5 HCGS FSAR OUESTION4804(NECTION6.2.1)
Satisfactory performance of the wetwell to drywell d
chugging phases of a LOCA for MARK I plants should be demonstrated.
In addition, we Provide your plans to resolve these concerns.
82 have reviewed the GE generic submittal (GE Letter IMFN-094-1982) on vacuum breaker actuation and haveTherefore, if dated July 2, concluded it is acceptable.
applicability of this generic submittal to your plant, the concern associated with pool swell will be satisfied.
RESPONSE
1982 is applicable to HCGS's GE Letter (MFN-094-82 dated July 2, suppression pool-to-d l
%ve. beem "Urecommendations from the Mark I BWR owne f Vacuum Breakers on Mark I
. Generic Letcer 83-08, Modifications o for Containments,4a plant unique calculation that forms the bases NRC for the vacuum breaker modification essei be submitted to I
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ATTACHMENT VIII
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l CEC 31 '84 0 2 7 61. 0 5 10/84 HCGS FSAR klerua.e f fN October 3, 1984.
The test report and an ssociated analysis of the test results will be submitted in ":::..L
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l An analysis has been performed to support the values used for the acceptance criteria for voltages.
This analysis shows that the voltages specified will not cause misoperation or loss of any electrical equipment connected to the supply buses.
The results of this analysis for the ac systems are stated in Section 8.3.1.2.1 and the calculated results are shown in Table 8.3-11.
The results of the de analysis are contained in Section 8.3.2.
These results indicate that the 125 volt de system has an i
acceptable operating capability with battery voltage variations j
of 35 volts (140 volts de to 105 volts dc).
The test acceptance criterion limits the bus voltage variation to 105-135 volts.
In addition, the acceptance values for the test currents are well below the level that would cause the infeed breakers to the UPS supply buses to trip.
These values are as follows:
Acceptance Infeed breaker Circuit Current Settino Normal 480 VAC 0-55 amperes continuous 600 amperes.
Supply with a maximum peak not pick-up to exceed 132 eunperes and no value above 55 amperes shall persist for longer k
j than 10 mS i
.Back-up 480 VAC 0-78 amperes continuous 600 amperes l
Supply with a maximum peak not Pick-up to exceed 500 amperes and no value above 78 amperes shall persist for longer than 10 mS Alternate 125 VAC The bus voltage. variation 2000 ampere i
Supply A
of 105-135 volts will hold fuse p
forthe following casos:
(i) With.the UPS energized j
but'without load the I
input current should not exceed 56 amperes I
(2) With the UPS input current at'56 amperes the input current should not exceed the range of 0 56 amperes V
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430.33-4 Amendment 8
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