ML19210D600: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
 
Line 27: Line 27:
During the subject meeting many items were discussed that were lef t unresolved or required further follow-up.
During the subject meeting many items were discussed that were lef t unresolved or required further follow-up.
Attached is a list of those items that we compiled.
Attached is a list of those items that we compiled.
Yours very truly, D. L. Aswell DIA:bar Attachment
Yours very truly, D. L. Aswell DIA:bar Attachment o
                                                                                                              ,
67O 7 9112 70 3c cf
                                                                                                .
o 67O 7 9112 70 3c cf


~
~
    ..
h NRC MEETING OCTOBER 30, 1979 ACTION ITEMS SCHEDULING
h NRC MEETING OCTOBER 30, 1979 ACTION ITEMS SCHEDULING
: 1. LP&L would like, for information only, a copy of draft safety review schedule within the next 3 or 4 weeks.
: 1. LP&L would like, for information only, a copy of draft safety review schedule within the next 3 or 4 weeks.
Line 54: Line 51:
: 2. NRC will issue another questien regarding Item 1.
: 2. NRC will issue another questien regarding Item 1.
                                                                               }}]
                                                                               }}]
      .


.
        .
      ,
9 TECHNICAL (cont'd)
9 TECHNICAL (cont'd)
: 3. CE will revise their response to NRC question 211.2.
: 3. CE will revise their response to NRC question 211.2.
Line 65: Line 58:
b) Add information ou GDC-15 and IEEE-279.
b) Add information ou GDC-15 and IEEE-279.
c) Identify the number of HPSI and/or charging pumps assumed to be operating.
c) Identify the number of HPSI and/or charging pumps assumed to be operating.
: 4. NRC will call regarding any significant differences between FSAR Subsection 6.2.1.1.3 under, " Environmental Design of Mechanical and Electrical Equip-
: 4. NRC will call regarding any significant differences between FSAR Subsection 6.2.1.1.3 under, " Environmental Design of Mechanical and Electrical Equip-ment," and the CSB interim evaluation model.
    ,
ment," and the CSB interim evaluation model.
: 5. LP&L will consider screens to preclude debris from preventing the large containment purge valves from fully closing. Ebasco will also do a detail review of the effects on any safety related components due to a failure of tha nonsafety containment purge duct work, filters, fans, etc. outside the containment. Upon completion Ebasco will revise the response to NRC question 22.08 and NRC will issue a new question regarding these items.
: 5. LP&L will consider screens to preclude debris from preventing the large containment purge valves from fully closing. Ebasco will also do a detail review of the effects on any safety related components due to a failure of tha nonsafety containment purge duct work, filters, fans, etc. outside the containment. Upon completion Ebasco will revise the response to NRC question 22.08 and NRC will issue a new question regarding these items.
: 6. NRC will send LP&L a copy of their draft NUREG on Environmental-Qualification.
: 6. NRC will send LP&L a copy of their draft NUREG on Environmental-Qualification.

Latest revision as of 04:17, 2 February 2020

Forwards List of Unresolved Items from Nrc/Util 791030 Meeting
ML19210D600
Person / Time
Site: Waterford Entergy icon.png
Issue date: 11/09/1979
From: Aswell D
LOUISIANA POWER & LIGHT CO.
To: Vassallo D
Office of Nuclear Reactor Regulation
References
LPL-12396, NUDOCS 7911270369
Download: ML19210D600 (3)


Text

. . . ...

LOUISIANA 242 octAnoNoe Srneer P O W E R & L i G H T! R O BOX 6000

  • NEW OnLEANS. LOUIStANA. (5041 366-2345 70174 sm UTiuTIES SYSTEM Vce Pres.oent-power producten November 9, 1979 LPL 12396 3-A12.05 Mr. Domenic B. Vassallo U.S. Nuclear Regulatory Commission Phillips Building 7920 Norfolk Avenue Bethesda, MD 26545

SUBJECT:

Waterford 3 - Docket 50-382 NRC - LP&L Meeting of October 30, 1979 Action Items

Dear Mr. Vassallo:

During the subject meeting many items were discussed that were lef t unresolved or required further follow-up.

Attached is a list of those items that we compiled.

Yours very truly, D. L. Aswell DIA:bar Attachment o

67O 7 9112 70 3c cf

~

h NRC MEETING OCTOBER 30, 1979 ACTION ITEMS SCHEDULING

1. LP&L would like, for information only, a copy of draft safety review schedule within the next 3 or 4 weeks.
2. LP&L would like a copy of the latest priority list of casework.
3. NRC is requested to send LP&L a schedule of FSAR review being done by the national labs and other consultants.
4. NRC is requested to send LP&L copies of two memos describing the management of'and restrictions on FSAR review by national labs and other consultants.
5. It was indicated that Round 2 questions from the hydrology branch may be sent to LP&L within 3 weeks.
6. It was indicated that a final approved schedule fer Waterford could be sent to LP&L by NRC in January, 1980. However, LP&L will be advised in advance if milestones such as SER or OL are impacted.
7. NRC indicated they will issue clarifying letters on TMI-2 short-term lessons learned and B&O Task Group in the near future.
8. LP&L will amend the FSAR to include TMI-2 lessons learned positions starting January, 1980 and to be 90% complete by June, 1980.
9. LP&L will provide a table for FSAR Chapter 1 showing where IMI-2 positions are addressed in the FSAR.
10. The NRC was asked to reconsider the Security Plan Review schedule to make their review compatible with initial fuel delivery dates of January, 1981.
11. NRC was asked to try to identify the milestone dates of all planned site visits to LP&L (e.g. I&C, Fire Protection, SQRT, Security, etc).
12. NRC will respond to Mr. Aswell's letter to Dr. Denton regarding additional NRC manpower.
13. NRC will issue minutes of September 25, 1979 site visit as soon as possible.
14. NRC will issue meeting minutes for this meeting in the near future.
15. NRC will advise of dates for kick-off meetings with National Lab people and other consultants and that a preplanned agenda would be used.

TECHNICAL , ,

1. LP&L will add instrument response times, and valve closure times to the response to NRC question 313.11
2. NRC will issue another questien regarding Item 1.]

9 TECHNICAL (cont'd)

3. CE will revise their response to NRC question 211.2.

Appendix 5.2B will be reorganized and cross references added in order to address each portion of Branch Technical Position 5-2. NRC will issue a new question which specifically mentions: a) Need more information in order to verify compliance with BTP5-2. b) Add information ou GDC-15 and IEEE-279. c) Identify the number of HPSI and/or charging pumps assumed to be operating.

4. NRC will call regarding any significant differences between FSAR Subsection 6.2.1.1.3 under, " Environmental Design of Mechanical and Electrical Equip-ment," and the CSB interim evaluation model.
5. LP&L will consider screens to preclude debris from preventing the large containment purge valves from fully closing. Ebasco will also do a detail review of the effects on any safety related components due to a failure of tha nonsafety containment purge duct work, filters, fans, etc. outside the containment. Upon completion Ebasco will revise the response to NRC question 22.08 and NRC will issue a new question regarding these items.
6. NRC will send LP&L a copy of their draft NUREG on Environmental-Qualification.
7. NRC will determine if they should revise their questions 110.1 and 231.2 regarding asymmetric loads.
8. LP&L will set up a meeting with Dr. Ho, the Navel Research Lab people,'

LP&L, and CE to discuss seismic qualification.

9. NRC was requested to tell LP&L if the SONGS test abstracts are satisfactory. .

e 1397 20L7}}