ML17054B537: 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)
 
(5 intermediate revisions by the same user not shown)
Line 3: Line 3:
| issue date = 04/03/1985
| issue date = 04/03/1985
| title = Forwards Program for Completion of Engineering Assurance In-Depth Technical Audits,Nine Mile Point 2 Project & Overall Audit Plan for RCIC Sys & Associated Structures,In Response to Questions from 850227 & 0315 Meetings
| title = Forwards Program for Completion of Engineering Assurance In-Depth Technical Audits,Nine Mile Point 2 Project & Overall Audit Plan for RCIC Sys & Associated Structures,In Response to Questions from 850227 & 0315 Meetings
| author name = MANGAN C V
| author name = Mangan C
| author affiliation = NIAGARA MOHAWK POWER CORP.
| author affiliation = NIAGARA MOHAWK POWER CORP.
| addressee name = SCHWENCER A
| addressee name = Schwencer A
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| docket = 05000410
| docket = 05000410
Line 15: Line 15:
| page count = 8
| page count = 8
}}
}}
=Text=
{{#Wiki_filter:f REGUL'A      Y  INFORMATION DISTRIBUTIONS% YSTEM (RIDS)
ACCESSION NSR:    8804090149, DOC, DATE: 88/04/03 NOTARIZED: NO                          DOCKET FACIL:50 BYNAME 410  Nine Mile Point Nuclear Station< Unit 2E Niagara                Moha  05000410 AUTH                  AUTHOR AFF ILIATION MANGANjC ~ VS        Niagara      Mohawk Power  Corp.
RECIP ~ NAME          RECIPIENT AFFILIATION SCHWENCEREA  ~    'icensing            Branch 2
==SUBJECT:==
Forwards "Program        f'r  Completion of Engineering Assur ance In-Depth Technical 'Audits" Nine Mile Point 2 ProJect L overall audit plan for RCIC sys 8, associated structuresEin response to questions from 850227 8 0315 meetings, DISTRIBUTION CODE: 8001D TITLE: Licensing COPIES RECEIVED:LTR Submittal: PSAR/FSAR Amdts L fRelated ENCL  g    SIZE; Correspondence NOTES REC IP IENT            COPIES            RECIPIENT              COPIES ID CODE/NAME            LTTR ENCL      ID CODE/NAME            LTTR ENCL' NRR/DL/ADL                  1    0      NRR L82 BC                        0 NRR L82 LA                  1    0      HAUGHEYEM          01      1 INTERNAL: ACRS                41        6    6      ADM/LFMB                          0 ELD/HDS3                    1    0      IE  F ILE                        1 IE/DEPER/EPB 36            1    1      IE/DGAVT/QAB21                    1 NRR ROEEM L                1    1      NRR/DE/AEAB                      0 NRR/DE/CEB        11        1    1      NRR/DE/EHEB                      1 NRR/DE/EQB NRR/DE/MEB 13 18 2.
1 2
1 NRR/DE/GB NRR/DE/MTEB 28 17 2'
NRR/DE/SAB        24        1    1      NRR/DE/SGEB        25            1 NRR/DHFS/HFE840            1    1      NRR/DHFS/LQB      32            1 NRR/DHFS/PSRB              1    1      NRR/DL/SSPB                      0 NRR/DSI/AEB ?6              1    1      NRR/DS I/ASB NRR/DSI/CPB      10        1    1      NRR/DS I/CSB      09            1 NRR/DSI/ICSB 16            1    1      NRR/DS I/METB      12            1 NRR/DSI/PSB      19        1    1                  /RAB  22            1 NRR/DS I/RSB 23            1    1        G  F IL        04            1 RGN1                        3    3                      8                0 EXTERNAL: BNL(AMDTS ONLY)              1    1      DMB/DSS (AMDTS)                  1 LPDR              03-      1    1      NRC PDR            02            1 NSIC              05        1    1      PNL GRUELiR                      1 TOTAL NUMBER OF COPIES REQUIRED: LTTR              51    ENCL
          'w I
N i
~
  't
                    '1 4
lf 4
Pg
0 Q gQOOlgg NIAGARA MOHAWK POWER CORPORATION/300 ERIE BOULEVARD WEST, SYRACUSE, N.Y. 13202/TELEPHONE (315) 4T4.15'I 1 April 3,    1985 (NMP2L 0378)
Mr . A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington,      DC 20555
==Dear Mr. Schwencer:==
Re:        Nine Mile Point Unit 2 Engineering Assurance Activities Docket No. 50-410 We    are transmitting with      this letter copies of the following:
: 1. Program for completion of the Engineering Assurance In-Depth Technical Audits Nine Mile Point 2 Project
: 2. Overall audit plan, guality Assurance Auditing Division, audit of as constructed condition of Reactor Core Isolation Cooling system and associated structures Nine Mile Point 2 Project In addition, we are providing the following information in response to key questions which were discussed during our meetings with the Nuclear Regulatory Commission on February 27, 1985 and March 15, 1985.
Selection of the      RCIC  S stem  to  be Audited The Reactor Core Isolation Cooling (RCIC) system has been selected                      as  the most appropriate system to be audited based on the following:
f Per or ms  safety related    functi on s Includes both Stone 5 Webster        and General Electric design responsibilities    and  interfaces    and is representative of        the Stone 5 Webster design process Contains  multi-discipline inputs        and involvement Interfaces with other systems 8504090i49 850403 PDR A
ADOCK 050004i0 PDR QoeI l(I
P c
  'I ii II l
l>
4 4 I1
( ~
Mr. A. Schwencer Page  2 t
Contains completed Class      1 piping analysis High energy system which allows for      inclusion of High Energy Line Break (HELB) analysis in the audit Although RCIC is not a system with parallel operating trains; the High Pressure Core Spray (HPCS) system performs a redundant function to  RCIC, hence,  single phase protection    may be verified for physical separation    and for separation  and independence  of electrical  power sources between these two systems.
Status of design/construction      completion in as  built reconciliation phase  - final stress    packages available The RCIC system has    not been previously subjected to an Engineering Assur ance  in-depth technical audit or similar evaluation for the Nine Mile Unit  2  project.
System was    previously within the scope of an in-depth techncial evaluation on another Stone & Webster project; the experience gained in that audit will facilitate an increase in depth of this audit.
It is  our conclusion that the RCIC system      is the most appropriate selection for    an  audit based on the above factors. The fact that this system was included within the scope of an in-depth technical evaluation at another Stone & Webster project will not adversely impact the validity of the audit on the Nine Mile Point 2 project as a basis for establishing confidence and adequacy of the design process and its implementation.          This conclusion is based primarily on the Stone & Webster project organization approach such that the Nine Mile Point Unit 2 audit will be an audit of the Stone & Webster design process as implemented by a different project team. In addition, corrective action, if any, taken by the Nine Mile Point Unit 2 project team as a result of the early audit will be included in developing overall conclusions.
Subcontracted    Desi n  Activities We have considered the need to include subcontracted        design work in the upcoming in-depth technical audit. We have established that Reactor Controls, Inc. (RCI) is the only contractor performing substantial safety related design work for the project. We believe that the technical audits of RCI, being performed as part of the Stone & Webster vendo~ audit program, and the site audits of RCI provide sufficient basis to conclude that RCI work need not be included in the upcoming Engineering Assurance in-depth technical audit of the p~oject.
The technical audits which have and are continuing to be performed on RCI are lead by Stone & Webster Engineering Assurance and include off-project experienced technical personnel on the audit team. We have separately provided the NRC with copies of the checklists and reports for these audits.
In addition to the technical audits, RCI site activities since 1982 have been audited several times by Stone & Webster guality Assurance and by Niagar a
f.
N      N I l l
g  W d t II ff
Mr. A. Schwencer Page  3 Mohawk's  guality Assurance Audit Group. Our ing these audits, samples of work in progress and completed work were examined for conformance to specifications, drawings and procedures. Niagara Mohawk guality Assurance has also performed a comprehensive surveillance program of RCI including reactor inter nals, reactor recirculation piping and control rod drive system installation activities. This surveillance has included substantially more than just the Enterprise and Multi-function support systems associated with the control rod drive system. These surveillance reports ar e available on site for your review. We will respond to any questions you have on these documents and adjust the scope of our vendor audits of RCI, if necessary, to resolve any concern that results from your review of these documents.
Evaluation of    AC Power  Oistribution    S stem The Engineering Assurance audit will include a substantial review of the electrical discipline design activities as it related to the RCIC system. The review will include a verification of the capability of the electrical distribution system to provide adequate power and voltage and to verify the separation    and independence of the system from power supply to the HPCS system. The audit will not include a review of other portions of the AC distribution system as similar reviews have been performed in the Stone &
Webster  New  York office independent evaluation.
Copies of the Stone & Webster New York office evaluation have been provided to the NRC under separate cover. We believe your review of this report will confirm the appropriateness of the planned scope in the electr ical discipline.
Selection of the Audit    Team  Personnel As  indicated in the attached audit plans, the Engineering Assurance audit team  will include off-project experienced technical personnel to provide for in-depth assessment of the design work. Similarly, the guality Assurance audit of the as constructed condition will be comprised of certified auditors with experience in the installation and inspection activities being audited.
Oetai led resumes of auditors are available for your review in the Stone &
Webster Boston office and at the site for the Niagar a Mohawk personnel.
Yery truly yours, C. V. Mang n Yice President Nuclear Engineering    &  Licensing AFZ:ja Attachment xc:  R. A. Gramm,  NRC  Resident Inspector J. Milhoan Project File (2)
4 4
\ hl 4
n' r I r
                  ~  ~
tl 14}}

Latest revision as of 07:58, 30 October 2019

Forwards Program for Completion of Engineering Assurance In-Depth Technical Audits,Nine Mile Point 2 Project & Overall Audit Plan for RCIC Sys & Associated Structures,In Response to Questions from 850227 & 0315 Meetings
ML17054B537
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 04/03/1985
From: Mangan C
NIAGARA MOHAWK POWER CORP.
To: Schwencer A
Office of Nuclear Reactor Regulation
Shared Package
ML17054B538 List:
References
NMP2L-0378, NMP2L-378, NUDOCS 8504090149
Download: ML17054B537 (8)


Text

f REGUL'A Y INFORMATION DISTRIBUTIONS% YSTEM (RIDS)

ACCESSION NSR: 8804090149, DOC, DATE: 88/04/03 NOTARIZED: NO DOCKET FACIL:50 BYNAME 410 Nine Mile Point Nuclear Station< Unit 2E Niagara Moha 05000410 AUTH AUTHOR AFF ILIATION MANGANjC ~ VS Niagara Mohawk Power Corp.

RECIP ~ NAME RECIPIENT AFFILIATION SCHWENCEREA ~ 'icensing Branch 2

SUBJECT:

Forwards "Program f'r Completion of Engineering Assur ance In-Depth Technical 'Audits" Nine Mile Point 2 ProJect L overall audit plan for RCIC sys 8, associated structuresEin response to questions from 850227 8 0315 meetings, DISTRIBUTION CODE: 8001D TITLE: Licensing COPIES RECEIVED:LTR Submittal: PSAR/FSAR Amdts L fRelated ENCL g SIZE; Correspondence NOTES REC IP IENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL' NRR/DL/ADL 1 0 NRR L82 BC 0 NRR L82 LA 1 0 HAUGHEYEM 01 1 INTERNAL: ACRS 41 6 6 ADM/LFMB 0 ELD/HDS3 1 0 IE F ILE 1 IE/DEPER/EPB 36 1 1 IE/DGAVT/QAB21 1 NRR ROEEM L 1 1 NRR/DE/AEAB 0 NRR/DE/CEB 11 1 1 NRR/DE/EHEB 1 NRR/DE/EQB NRR/DE/MEB 13 18 2.

1 2

1 NRR/DE/GB NRR/DE/MTEB 28 17 2'

NRR/DE/SAB 24 1 1 NRR/DE/SGEB 25 1 NRR/DHFS/HFE840 1 1 NRR/DHFS/LQB 32 1 NRR/DHFS/PSRB 1 1 NRR/DL/SSPB 0 NRR/DSI/AEB ?6 1 1 NRR/DS I/ASB NRR/DSI/CPB 10 1 1 NRR/DS I/CSB 09 1 NRR/DSI/ICSB 16 1 1 NRR/DS I/METB 12 1 NRR/DSI/PSB 19 1 1 /RAB 22 1 NRR/DS I/RSB 23 1 1 G F IL 04 1 RGN1 3 3 8 0 EXTERNAL: BNL(AMDTS ONLY) 1 1 DMB/DSS (AMDTS) 1 LPDR 03- 1 1 NRC PDR 02 1 NSIC 05 1 1 PNL GRUELiR 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 51 ENCL

'w I

N i

~

't

'1 4

lf 4

Pg

0 Q gQOOlgg NIAGARA MOHAWK POWER CORPORATION/300 ERIE BOULEVARD WEST, SYRACUSE, N.Y. 13202/TELEPHONE (315) 4T4.15'I 1 April 3, 1985 (NMP2L 0378)

Mr . A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555

Dear Mr. Schwencer:

Re: Nine Mile Point Unit 2 Engineering Assurance Activities Docket No. 50-410 We are transmitting with this letter copies of the following:

1. Program for completion of the Engineering Assurance In-Depth Technical Audits Nine Mile Point 2 Project
2. Overall audit plan, guality Assurance Auditing Division, audit of as constructed condition of Reactor Core Isolation Cooling system and associated structures Nine Mile Point 2 Project In addition, we are providing the following information in response to key questions which were discussed during our meetings with the Nuclear Regulatory Commission on February 27, 1985 and March 15, 1985.

Selection of the RCIC S stem to be Audited The Reactor Core Isolation Cooling (RCIC) system has been selected as the most appropriate system to be audited based on the following:

f Per or ms safety related functi on s Includes both Stone 5 Webster and General Electric design responsibilities and interfaces and is representative of the Stone 5 Webster design process Contains multi-discipline inputs and involvement Interfaces with other systems 8504090i49 850403 PDR A

ADOCK 050004i0 PDR QoeI l(I

P c

'I ii II l

l>

4 4 I1

( ~

Mr. A. Schwencer Page 2 t

Contains completed Class 1 piping analysis High energy system which allows for inclusion of High Energy Line Break (HELB) analysis in the audit Although RCIC is not a system with parallel operating trains; the High Pressure Core Spray (HPCS) system performs a redundant function to RCIC, hence, single phase protection may be verified for physical separation and for separation and independence of electrical power sources between these two systems.

Status of design/construction completion in as built reconciliation phase - final stress packages available The RCIC system has not been previously subjected to an Engineering Assur ance in-depth technical audit or similar evaluation for the Nine Mile Unit 2 project.

System was previously within the scope of an in-depth techncial evaluation on another Stone & Webster project; the experience gained in that audit will facilitate an increase in depth of this audit.

It is our conclusion that the RCIC system is the most appropriate selection for an audit based on the above factors. The fact that this system was included within the scope of an in-depth technical evaluation at another Stone & Webster project will not adversely impact the validity of the audit on the Nine Mile Point 2 project as a basis for establishing confidence and adequacy of the design process and its implementation. This conclusion is based primarily on the Stone & Webster project organization approach such that the Nine Mile Point Unit 2 audit will be an audit of the Stone & Webster design process as implemented by a different project team. In addition, corrective action, if any, taken by the Nine Mile Point Unit 2 project team as a result of the early audit will be included in developing overall conclusions.

Subcontracted Desi n Activities We have considered the need to include subcontracted design work in the upcoming in-depth technical audit. We have established that Reactor Controls, Inc. (RCI) is the only contractor performing substantial safety related design work for the project. We believe that the technical audits of RCI, being performed as part of the Stone & Webster vendo~ audit program, and the site audits of RCI provide sufficient basis to conclude that RCI work need not be included in the upcoming Engineering Assurance in-depth technical audit of the p~oject.

The technical audits which have and are continuing to be performed on RCI are lead by Stone & Webster Engineering Assurance and include off-project experienced technical personnel on the audit team. We have separately provided the NRC with copies of the checklists and reports for these audits.

In addition to the technical audits, RCI site activities since 1982 have been audited several times by Stone & Webster guality Assurance and by Niagar a

f.

N N I l l

g W d t II ff

Mr. A. Schwencer Page 3 Mohawk's guality Assurance Audit Group. Our ing these audits, samples of work in progress and completed work were examined for conformance to specifications, drawings and procedures. Niagara Mohawk guality Assurance has also performed a comprehensive surveillance program of RCI including reactor inter nals, reactor recirculation piping and control rod drive system installation activities. This surveillance has included substantially more than just the Enterprise and Multi-function support systems associated with the control rod drive system. These surveillance reports ar e available on site for your review. We will respond to any questions you have on these documents and adjust the scope of our vendor audits of RCI, if necessary, to resolve any concern that results from your review of these documents.

Evaluation of AC Power Oistribution S stem The Engineering Assurance audit will include a substantial review of the electrical discipline design activities as it related to the RCIC system. The review will include a verification of the capability of the electrical distribution system to provide adequate power and voltage and to verify the separation and independence of the system from power supply to the HPCS system. The audit will not include a review of other portions of the AC distribution system as similar reviews have been performed in the Stone &

Webster New York office independent evaluation.

Copies of the Stone & Webster New York office evaluation have been provided to the NRC under separate cover. We believe your review of this report will confirm the appropriateness of the planned scope in the electr ical discipline.

Selection of the Audit Team Personnel As indicated in the attached audit plans, the Engineering Assurance audit team will include off-project experienced technical personnel to provide for in-depth assessment of the design work. Similarly, the guality Assurance audit of the as constructed condition will be comprised of certified auditors with experience in the installation and inspection activities being audited.

Oetai led resumes of auditors are available for your review in the Stone &

Webster Boston office and at the site for the Niagar a Mohawk personnel.

Yery truly yours, C. V. Mang n Yice President Nuclear Engineering & Licensing AFZ:ja Attachment xc: R. A. Gramm, NRC Resident Inspector J. Milhoan Project File (2)

4 4

\ hl 4

n' r I r

~ ~

tl 14