ML20133F759
| ML20133F759 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 08/05/1985 |
| From: | Mittl R Public Service Enterprise Group |
| To: | Butler W Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8508080421 | |
| Download: ML20133F759 (18) | |
Text
,V O PS G Cornpany PubLc Serwce Electnc and Gas 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 August 5, 1985 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20814 Attention:
Mr. Walter Butler, Chief Licensing Branch 2 Division of Licensing Gentlemen:
IlOPE CREEK GENERATING STATION DOCKET NO. 50-354 FSAR COMMITMENT STATUS THROUGH JULY 1985 Public Service Electric and Gas Company presently plans to issue Amendment No. 12 to the Hope Creek Generating Station Final Safety Analysis Report by September 18, 1985.
Accord-ingly, this letter is provided to document the status of Hope Creek Generating Station responses to FSAR commitments which were forecasted to be responded to by June and July 1985.
Attachment I is a tabulation of the Hope Creek Generating Station Final Safety Analysis Report commitments for June and July 1985, and the corresponding resolution for each commitment.
Attachments II through VI provide responses to commitments forecasted to be responded to in June and July 1985.
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t The Energy People
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Director of Nuclear Reactor Regulation 2
8/5/85 Should you have any questions in this regard, please contact us.
Very truly y urs, llV N Attachment I
- Hope Creek Generating Station - FSAR L
Commitment Status through July 1985 Attachment II
- Response to Question 100.6 (TMI III.D.3.3)
Attachment III
- Response to Question 421.24 i
Attachment IV
- Response to Question 471.7 Attachment V
- Response to Question 630.7g Attachment VI-
- Response to FSAR Section 9.3.2.3.2.b.1 i
C D.
H. Wagner (w/ attach)
USNRC Licensing Project Manager i
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Blough (w/ attach)
USNRC Senior Resident Inspector i
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ATTACHMENT I Page 1 of 6 HOPE CREEK GENERATING STATION FSAR COMMITMENT STADJS THROUGH JULY 1985 FSAR Ccmnitment location Comnitment Resolution FSAR CONITMENIS FCR JUNE 1985
- 1. ESAR Section 1.14.1.46.2 This ccmnitment concerns formulating and implementing a training program for Station Blackout. A training program has been implemented at Hope Creek. This information will be incorporated into the HOGS FSAR.
- 2. FSAR Section 1.14.1.66.2 This ccanitment concerns providing an Emergency Operating Procedure for cold shutdown upon loss of power to Class lE and Non-Class lE I&C buses.
This procedure is avai?.able for review. This information will be incorporated into the H(IIS ESAR.
- 3. FSAR Table 13.1-4 This ccanitment concerns providing resumes for Sr. Radiation Protection Supervisor and Sr. Radiological Engineer. This information will be provided in September 1985.
- 4. Question / Response Appendix:
This cennitment concerns providing a Question 100.6 description of equipment, training, (TMI Item III.D.3.3.)
and procedures necessary to determine airborne radio-iodine concentration.
This information has been provided in Amendment 11 to the HCI;S ESAR and is response to HCI3S SE1 Confirmatory Issue No. 35. Reference to this information is provided in Attachnent II and will be included in Amendment 12 to the HOG 3 FSAR.
- 5. Question / Response Appendix:
This ccanitment concerns providing Question 220.10 procedures for functional testing, channel checks, and calibration of seismic instrumentation. This infor-nation will be provided by September 1985.
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ATTACHMENT I Page 2 of 6 HOPE CREEK GENERATING STATION FSAR COMMI'IMENT STATUS 'IHROUGH JULY 1985 4
FSAR Cmmitment Location Comnitment Resolution
- 6. Question / Response Appendix:
Eis ccmnitment concerns providing a Question 410.1 procedure to bring the reactor to a cold shutdown for plant flood condi-tions. This procedure is available for review. This information will be incorporated into the HCIiS FSAR.
- 7. Question / Response Appendix:
This ccanitment concerns providing Question 410.87 preventive maintenance procedures for Moisture Separator, Emergency Instru-ment Air Ccunpressor and Instrument Air Filter changeout. These proce-dures are available for review. This information will be incorporated into the HCIIS ESAR.
- 8. Question / Response Appendix:
his ccmnitment concerns providing Question 421.13 test results for isolation devices.
This infonnation, which regards HOGS i
SER Confinnatory Issue No.17, will be provided by October 1985.
- 9. Question / Response Appendix:
'Ihis ccmnitment concerns providing Question 421.24 the HO3S Technical Specifications.
'Ihis information has been subnitted for NRC review (letter from R. L.
Mittl, PSE&G, to A. Schwencer, NRC, l
dated January 17, 1985). This reference information is provided in Attachment III and will be included in Amendment 12 to the HO3S ESAR.
4
- 10. Question / Response Appendix:
(See 'IMI Item III. D.3.3. above)
Question 471.7 Reference to this information is pro-vided in Attachment IV and will be l'ncluded in Amendment 12 to the HCI3S FSAR.
- 11. Question / Response Appendix:
This ccmnitment concerns providing Question 630.79 procedures for replacement training (Hot Licenses) for NRC candidates.
M P85 139/15 2-dh
ATTACHMENT I Page 3 of 6 HOPE CREEK GENERATIfG STATION FSAR COMMITNENT STAItJS THROUGH JULY 1985 FSAR Ccanitment Iocation Ccmnitment Resolution
- 11. Question / Response Appendix:
Information is provided in Question 630.7g (Cont'd)
Attachment V and will be included in Amendment 12 to the HOGS FSAR.
- 12. Supplemental Request for This ccanitment concerns implementing Additional Information Appendix:
an emergency procedure and a training SRAI (6) program for Station Blackout events.
An abnormal procedure and a training program for these events have been implemented at Hope Creek. This information will be incorporated into the HWS FSAR.
FSAR COMMITNENIS EUR JULY 1985
- 13. FSAR Section 1.14.1.27.2 This ccanitment concerns demonstrat-iry adequate core cooling is main-tained with LPCI diversion. This information has bcen provided in Amendment 10 to the HOGS FSAR and is response to HOGS SER Confirmatory Issue No. 14.
- 14. FSAR Section 1.14.1.108.2 This coninitment concerns assuring that the ECCS analysis considers fura cladding swelling and rupture. This information has been provided in Amendment 10 to the HGS FSAR and is response to HWS SER Confirmatory Issue No. 14.
- 15. ESAR Section 12.3.4.2.2 This ccrinitment concerns providing locations of portable air nonitors within the Hope Creek station. This information was submitted to NRC in letter frcm R. L. Mittl, PSE&G, to W. Butler, NRC, dated July 1,1985, as response to HG;S SER Confirmatory Issue No. 32. This information will be included in Amendment 12 to the HWS ESAR.
M P85 139/15 3-dh
ATTACHMENT I Page 4 of 6 HOPE GEEK GENERATI?G STATION FSAR COMMIINENT STATUS THROUGH JULY 1985 FSAR Cmmitment Incation Cm mitment Resolution
- 16. FSAR Section 12.5.2.2 This cmmitment concerns providing onsite calibration capability details for instruments and equipnent. This information was sutmitted to NRC in letter fran R. L. Mittl, PSE&G, to W. Butler, NRC, dated July 1,1985, as response to HQS SER Confirmatory Issue No. 34. This information will be included in Amendment 12 to the HCI3S FSAR.
- 17. FSAR Table 15.6-7 This cmmitment concerns providing an ECCS analysis events list for a steam line break. This information has been provided in Amendment 10 to the HCI3S FSAR.
- 16. Question / Response Appendix:
This cmmitment concerns providing Question 230.8 seismic information. This informa-tion has been provided in Amendment 8 to the HGS ESAR.
- 19. Question / Response Appendix:
This cmmitment concerns providing Question 410.87 periodic testing procedures for the instrument air system. These proce-dures are available for review. This information will be incorporated into the HOGS FSAR.
- 20. Question / Response Appendix:
This carmitment concerns providing a Question 440.0 plant-specific If)CA analysis. This information has been provided in Amendment 10 to the HCI3S FSAR.
- 21. Question / Response Appendix:
This cmmitment concerns providing Question 440.27 references for model changes regard-ing the HCI3S ECG analysis. This information has been provided in Amendment 10 to the HCI3S FSAR.
M P85 139/15 4-dh
ATTACHMENT I Page 5 of 6 HOPE CREEK GENERATIfC STATION FSAR COMMITNENT STATUS THROLEH JULY 1985 l
FSAR Cartunitment Iocation Certinitment Resolution
- 22. Question / Response Appendix:
This cmmitment concerns providing Question 440.28 the IDCA analysis. This information has been provided in Amendment 10 to the HCES FSAR.
- 23. Question / Response Appendix:
This ccmnitment concerns conducting Question 630.11 an NRC instructor certification examination using the HCES simula-tor. This examination has been con-ducted and the NRC has reviewed the capabilities of the HWS simulator.
This information will be incorporated into the HCES FSAR.
FSAR COlHITNENIS PAST DUE AND REIORECASTED TO JULY 1985
- 24. FSAR Section 9.3.2.2.2.11 This cmmitment concerns providing procedures for disposal of lab sanr-ples. These procedures are available for review. This information will be incorporated into the HOGS FSAR.
- 25. FSAR Section 9.3.2.3.2.b.1 This ccmnitment concerns providing a plant specific procedure to assess the extent of core damage based on radio nuclide concentrations and other parameters in fulfillment of IKGS SER Confirmatory Issue No. 31.
This information is provided in Attachment VI and will be included in Amendment 12 to the HCES ESAR.
- 26. Question / Response Appendix:
This ctanitment concerns providing Question 210.20 the Feedwater Isolation Check Valve Analysis results. This information was suttnitted to the NRC in a letter fran R. L. Mittl, PSE&G, to W. Butler, NRC, dated July 1,1985, in response to HWS SER Confirmatory Issue No. 1.
This information will be included in Amendment 12 to the H(ES FSAR.
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ATTACHMENT I Page 6 of 6 HOPE GEEK GENERATItG STATION FSAR COMMITMENT STATUS THROUGH JULY 1985 FSAR Cmmitment Incation Commitment Resolution
- 27. Question / Response Appendix:
This comnitment concerns updating Question 210.21 FSAR Section 3.6 tables and figures for final stress analysis results.
This information is pending NRC acceptance of PSE&G's proposed pipe break location eliminations.
- 28. Question / Response Appendix:
(See Question 210.21 above.)
Question 210.24
- 29. Question / Response Appendix:
This cmmitment concerns developing a Question 281.14 program to monitor the Boral surveil-lance program at an operating plant.
An agreement with the Monticello plant has been made. This informa-tion will be incorporated into the HCI;S FSAR.
- 30. Question / Response Appendix:
This cmmitment concerns providirg trip settings for the leak detection system. This information will be provided in August 1985.
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Response
ho5 hexan A description of the equipment, training, and procedures x.11 be provided by Jun; ;, i965.
in 5cchon /2. 5 3 -
e III.D.3.4 CONTROL ROOM HABITABILITY Position In accordance with Item III.D.3.4, " Control Room Habitability",
applicants shall assure that control room operators will be adequately protected against the effects of accidental release of toxic and radioactive gases and that the nuclear power plant can be safely operated or shut down under design basis accident conditions (GDC 19).
Clarification (1)
All applicants must make a submittal to us regardless of whether or not they met the criteria of the referenced Standard Review Plan sections.
The new clarification specifies that applicants that meet the criteria of the Standard Review Plans should provide the basis for their conclusion that Section 6.4 of the Standard Review Plan requirements are met.
Applicants may establish this basis by referencing past submittals to us and/or providing new or additional information to supplement past submittals.
(2)
All applicants with control rooms that meet the criteria of the following sections of the Standard Review Plan:
2.2.1,2.2.2 Identification of Potential Hazards in Site
- Vicinity, 2.2.3 Evaluation of Potential Accidents, and 6.4 Habitability Systems shall report their findings regarding~the specific Standard Review Plan sections as explained below.
The folicwing documents should be used for guidance:
1.10-98 Amendment 5
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ATTACHMENT III 6
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QUESTION 421.24 (SECTIONS 7.2, 7.3, 7.4, 7.5, 7.6, & 7.7)
Section 7.3.1.2 of the FSAR references Chapter 16_of_the minimum number of sensors required to monitor safety-related variables.
Chapter 16 of the FSAR has not yet been subattted by the applicant.
For each monitored variable that provides an input to a safety-related system (i.e.,
reactor trip, engineered safety features, reactor core isolation cooling, recir. pump trip, control rod block) list the total number of channels provided and the minimum number of channels required to be operable that will be proposed in Chapter 16.
Confirm that tne single failure criterion can be satisfied for each case where the minimum number of operable channel requirements that will be proposed is less than the total number of channels provided.
RESPONSE
Chapter 16, " Technical Specifications,"
in the format of NUREG-0123,, 6 submitted m
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t le,- nac. toieQteA rd-on a t y n, r. A :amea ac, JAJ T.~ <y,
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HCGS safety-related systems are designed to conform with the requirements of IEEE Standard 279-1971.
Paragraph 4.11 specifically requires that "the system shall be designed to permit any one channel to be maintained, and when required, tested or calibrated during power operation without initiating a protective action at the systems level.
During such operation the active parts of the system shall of themselves continue to meet the single failure criterion."
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& Any discrepancies $ this licensing commitment m
.., ; 1 1 be corrected or satisfactory justification for the deviation will be provided to the NRC on a case by case basis.
Design drawings in the form of elementary diagrams, P& ids, logic diagrams, instrument location drawings, and electrical drawings from which Chapter 16 information will be extracted, have been provided to the NRC under separate cover and are listed in Tables 1.7-1, 1.7-2, and 1.7-3.
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ATTACHMENT IV l
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. 8'83 OUESTION 471.7 (SECTION 12.5.2)
Provide a schedule for submittal of your response to NUREG-0737, Item III.D.3.3, Improved Inplant Iodine Instrumentation Under Accident Conditions.
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RESPONSE
Specific details on the equipment, procedures, and training for deter.T.ining airborne iodine concentrations in the plant under bag J t e.r accident conditions, to meet the intent of NUREG-0737)
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HCGS FSAR 10/84 Applicable references for each of the segments outlined in l
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the appendices are shown on the appropriate cover sNeet df
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each appendix.
d.
Training segments which include 10CFR Part 55 Section 21, 22 and 23 are identified in Appendix 13A, 13C, 13E, 13F and 13G.
The following segments of the training program are still e.
under development:
Appendix I -
Cold license operator in-plant training Appendix J -
Pre-license examination testing and training f.
A course description for sognerts i and j of the training program is contained in Appendices 13 I and 13 J, respectively.
Appendix 13K pecivides a description of on-shift operating experience training.
e Hot license training for NRC candidates will be conducted to g.
augment the shift staffing allotment, allow for promotion or x
fill vacancies due to reassignment.
This training will utilize a major portion of the existing cold license training program; however, c,ertain areas may be waived based on an indivic'aal's prior experience and educational background.
Procedures describing the content and administrative requirement.s m ii 2
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Appendix 13F has been rev ed to incorpo' rate this response.
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However, NUREG 0737 Section II.B.3.1 requires that the PASS meet the following:
a.
The licensee shall have the capability to promptly obtain reactor coolant samples and containment atmosphere samples.
The combined time allotted for sampling and analysis should be 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> or less from the time a decision is made to take a sample.
The following is a conservative time sequence for sampling, transport, and analysis to demonstrate that samples can be obtained and analyzed within the specified 3-hour period:
1.
Recirculate sample, install sample vial /or cartridge -- 15 min.
2.
Operate sample station -- 15 min.
3.
Transport sample to lab -- 20 min.
4.
Analyze sample --- 30 min.
Sample points and sample gather'ng methods are discussed in Section 9.3.2.2.2.
b.
The licensee shall establish an onsite radiological and chemical analysis capability to provide, within the 3-hour time frame established above, quantification of the following:
1.
Certain radionuclides in the reactor coolant and containment atmosphere that may be indicators of the degree of core damage (e.g., noble gases; iodines and cesiums, and nonvolatile isotopes);
A generic procedure to assess the extent of core damage based on radionuclide concentrations and other parameters has been prepared by the BWR Owners Group (FSAR Section 1.8.1.97).
A HCGS plant-specific procedure based on this methodology has bve a sill be prepared by -Wil 105. ud wets su umitted l}& b L: the k L st f e t tgV, f. L M.4t I, PWG, so W.6u4fershtc.,
e Hydrogen levels in the containment atmosphere; g,gge 2 4 ig gr 2.
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At greater than 15% power, the primary containment i
atmosphere is maintained under a nitrogen blanket.
Hydrogen and oxygen concentrations are monitored by chemical analysis of gas samples drawn from various points in the drywell and torus.
During
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post accident conditions, hydrogen and oxygen 9.3-19 Amendment 10
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