ML20100J866
| ML20100J866 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 04/04/1985 |
| From: | Mittl R Public Service Enterprise Group |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8504110387 | |
| Download: ML20100J866 (9) | |
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Pubhc Service Electnc and Gas Company 80 Park Plaza, Newark, NJ 07101/ 201430-8217 MAILING ADDRESS / P.O. Box 570, Newark, NJ 07101
- Robert L. Mitti General Manager Nuclear Assurance and Regulation April 4, 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 MARCH 1985 Public Service Electric and Gas Company presently plans to issue Amendment No. 10 to the Hope Creek Generating Station Final Safety Analysis Report by May 1, 1985.
Accordingly, 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 February 1985 and March 1985.
Attachment I is a tabulation of the Hope Creek Generating Station Final Safety Analysis Report commitments for February 1985 and March 1985, and the corresponding resolution for each commitment.
Attachment II provides responses to commitments forecasted to be responded to in March 1985, which will be included in Amendment No. 10.
8 8504110387 850404 i
PDR ADOCK 05000354 l
A PDR The Energy People
%4912 (4V) 7 83
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1 Director of Nuclear-Reactor; Regulation.
2 4/4/85 Sh'ould you have any questions in. this regard, please contact us.
Very truly yours,
k g'/
I i
' Attachment I
- Hope ' Creek Generating Station - FSAR Commitment Status through March 1985 Attachment II
- Response to FSAR Sections 1.14.1.47.2 and 15.8.1 C
D.
H. Wagner (w/ attach)
USNRC Licensing Project Manager-A.
R..Blough (w/ attach)
USNRC Senior Resident Inspector
[
' MP84 123/06 1/2
Page 1 of 4 ATTACHMENT I HOPE CREEK GENERATING STATION FSAR COMMITMENT STATUS THROUGH MARCH 1985 FSAR Commitment Location Commitment Resolution
- 1. FSAR Section 1.14.1.47.2 This commitment concerns providing an emergency operating procedure for reactor control.for an ATWS event.
This information is provided in Attachment II and will be included in Amendment 10 to the HCGS FSAR.
2' FSAR Section 1.14.1.66.2 This commitment concerns providing an emergency operating procedure for cold shutdown upon loss of Class lE and non-Class lE I&C buses.
This information will be provided in June 1985.
This revised commitment date will be included in Amendment 11 to the HCGS FSAR.
- 3. FSAR Section 3.4.1.1 This commitment concerns providing an abnormal operating procedure for
" Acts of Nature."
This information-is available for review and is being submitted to NRC Region I.
Bypass Leakage Analysis.
PSE&G will submit a response to SER Confirmatory Item No.
13 by April 15, 1985, addressing this commitment.
NRC response to this submittal will be required to' fulfill this commitment.
MP 85'64/15 1-mr o
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Pcgo 2 of 4 ATTACHMENT I HOPE CREEK GENERATING. STATION FSAR COMMITMENT STATUS'THROUGH MARCH 1985 FSAR Commitment Location Commitment Resolution
- 5. FSAR Section 9.5.1.5.3 This commitment concerns providing fire protection administrative procedures.
This information is available for review.
- 6. FSAR Table 12.2-107 This commitment concerns providing radiation information on the dry radwaste container in this table.
This information will be provided in April 1985.
- 7. FSAR Table 13.1-la This commitment concerns providing resumes for Nuclear Department management and technical services and support personnel in response to HCGS SER Open Item No. 11.
Public Affairs Manager -
Nuclear position has been filled and the resume will be included in Amendment 10 to the HCGS FSAR.
The remaining resumes will be submitted as these positions are filled.
'8. FSAR Section 15.8.1 (See FSAR Section 1.14.1.47.2 above)
- 9. Question / Response Re:
TMI Item I.C.1; This Appendix:
commitment concerns Question 100.6 providing EOPs based on the PGP which contains emergency procedure guidelines.
EOPs are available for review and are being submitted to NRC Region I.
MPRB5 64/15 2-mr l'. _ _
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Page 3 of 4 ATTACHMENT I.
HOPE CREEK GENERATING STATION FSAR COMMITMENT. STATUS THROUGH MARCH 19851
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i FSAR Commitment' Location Commitment ~ Resolution
- 9. Question / Response Re: TMI Item I.C.5;.This Appendix:
(Cont'd) providing a procedure to commitment concerns ~
Ouestion 100.6 assure feedback of operating experience.
This procadure is available-for review.
RRe:.TMI Item I.C 8; This commitment concerns providing the PGP and plant
. specific emergency instructions.
The PGP has been provided-in letter; R.
L.- Mittl,. PSE&G. to A. Schwencer, NRC, dated January 28, 1985.
EOPs are available for review and are being suamitted to NRC Region I.
'Re:
TMI Item II.B.1; This commitme nt concerns provid-ing EOPs for H PCI, RCIC, and
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ADS.
EOPs are available for review and are being
-submitted to NRC Region I.
Re: TMI-Item II.K.l.5; This commitment concerns providing procedures to
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assure.that engineered safety features function properly.-
Procedures are available for review.
Re: TMI' Item II.K.l.10; This commitment concerns providing procedures for safety-related systems to assure operability status.
Procedures ' are ~ available for _
review and are being submitted to NRC Region I.
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Page 4 of 4 ATTACHMENT I HOPE CREEK GENERATING STATION
.FSAR COMMITMENT STATUS THROUGH MARCH 1985 FSAR -Commi tme nt Location Commitment Resolution
- 9. Question / Response Re: TMI Item II.K.3.16; This Appendix:
commitment concerns Question 100.6-(Cont'd) providing preventive maintenance procedures for SRVs.
Procedures are available for review.
- 10. Question / Response This commitment concerns Appendix; providing seismic Question 271.6 information in FSAR Table 3.10-3.
This information will be provided in September 1985.
This revised commitment date will be included in Amendment 11 to the HCGS FSAR.
11.-Question / Response.
This commitment concerns Appendix:
developing a program to Question 281.14_
monitor a Boral surveillance program within the industry in response to HCGS DSER Open Item No. 140.
This information will be provided' in May 1985.
- 12. Question / Response (See PSAR Section 3.4.1.1 Appendix:
above)
Question 410.4
- 13. Quest' ion / Response This commitment concerns Appendix:
addressing ste. tion blackout Ouestion 430.31 events by loss of electrical power procedure in compliance with NRC Generic Le tter 81-04.
This procedure is available for review.
- 14. Question / Response This commitment concerns Appendix:
providing details of HCGS Question 460.16 implementation of 10CFR61 requirements related to licensed burial facility.
This information will be provided in April 1985.
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e ATTACHMENT II 9
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1.14.1.46.1 Issue TMI Action Plan Item I.G.1 indicated the need to supplement operator training by completing a special low-power test program.
Further clarification of this item includes the need to perform a simulated loss of ofsite and onsite ac power.
1.14.1.46.2
Response
i See Section 1.10, Item I.G.1, for a discussion of operator -
training during low-power testing.
The Nuclear Training Center will formulate and implement a training programfor station j
blackout by June 1985, i
1.14.1.47 Emeroency procedures Reactivity Control Guidelines.
1 LRG II/2-HFS 1.14.1.47.1 Issue Develop a generic reactivity control guideline which can be utilized for preparing an emergency operating procedure for an anticipated transient without scram (ATWS) event.
1.14.1.47.2
Response
H will se the lat t emergency pro edure gq deli vs (eve}oped by he BWR nors' Grou.
These\\ proc ces wiln be avail %ble by Mar 1,
19 A c. (a, S E m s.qeac 4 o pers.+in3 Pre. t e et ur e.,
O A ~ C O. 32.
t o /, R ec e fcr-Centrol, t.on tson s th e necessa.ry ac.+ ions s + e be hs.Nen dw'*$ cis ATu)3 av en t.
1.14.1.48 Common Reference For Reactor Vessel Level Measurement. LRG II/3-HFS 1.14.1.48.1 Issue The NRC has asked that a common reference level be established for reactor water level instruments.
This is TMI action item II.K.3.27.
1.14-44 Amendment 1
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HCGS FSAR 1/84 15.8 ANTICIPATED TRANSIENTS WITHOUT SCRAM i
15. 8~.1 REQUIREMENTS The issue of postulated failure to scram the reactor following an anticipated transient, i.e.,
an anticipated transient without scram (ATWS), has been under consideration by the NRC.
As a i
result of its assessment, the NRC has required the recirculation pump trip (RPT) feature for the boiling water reactor (BWR).
It should be noted that the NRC has determined that the probability of an ATWS event is acceptably small, and that any i
additional plant modifications for ATWS need not satisfy the requirements for a design basis accident.
The HCGS emergency operating procedures will be developed from the BWR Owners' Group Generic Emergency Procedure Guidelines.
ATWS events are covered in these guidelines.
The Hope Creek
- 1C'1 Generating Station Emergency Operating Procedure. OP-EO.ZZ g
Reactor Control, will be d "=1c;-4 by Jrrun 790 tog-eLJ ;;11-containSthe necessary actions to be taken during an ATWS event.
operators, and shif t technicat advisers will incorporate the Training programs for reactor operators, senior reactor bases and philosophy of the GE/BWR Owners' Group generic emergency operating procedures until such time as the HCGS emergency operating procedures are developed.
i 15.8.2 PLANT CAPABILITIES I
The Hope Creek Generating Station (HCGS) design uses diverse, highly redundant, and very reliable scram systems.
This includes the normal scram systems, plus the electrically-diverse alternate rod inseetion (ARI) system.
Each of these systems is frequently tested and would insert the control rods even if multiple component failures should occur, thus making the probability of i
an anticipated transient without scram (ATWS) event extremely remote.
i The ATWS recirculation pump trip (RPT) feature prevents reactor vessel overpressure and possible short-term fuel damage for the most limiting postulated ATWS event.
Subsequent to an ATWS event for which the ARI system does not insert the control rods, the long-term shutdown of the reactor can be accomplished by either 15.8-1 Amendment 4
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