ML20091A233
| ML20091A233 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 09/30/1976 |
| From: | Mayer L NORTHERN STATES POWER CO. |
| To: | Ziemann D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20091A235 | List: |
| References | |
| NUDOCS 9105140459 | |
| Download: ML20091A233 (3) | |
Text
--
~
NSE3 NORTHERN STATES POWER C0MPANY M sNNea mou s. uiN N E SOTA SS40s 7
e Regulatory Docket FiW "0!%g September 30, 1976 M
p L
9 4
-C
,N\\. t ii t~N' p
t q.
Mr D L Ziemann, Chief gy M g
t\\
/p[
Q Operating Reactors Branch # 2 4
f
_l Division cf Operating Reactors
, N p p et**g [* O 4
U S Nuclear Regulatory Cotunission YW l
Washington, DC 20555
\\
f/
Dear Mr Ziemann:
/
MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22
_ Revision of Operational Quality Assurance Plan l
Our letter dated June 17, 1976 transmitted the NSP Operational Quality Assurance Plan, Revision 0, dated June 9,1976.
Subsequent to its sub-mittal, we have had discussions with the Regulatory Staff on additional information that is needed to complete their review of the plan. We have also now secured copies of the approved standard, ANSI N18.7-1976.
On the basis of this additional information, the Operational Quality Assur-ance Plan has been revised and 40 copies of Revision 1 to the plan, dated September 24, 1976 are submitted herewith for the docket listed above.
It is requested that this letter of transmittal and the attached plan supersede, in entirety, the previous submittal.
The operational quality assurance programs for the Monticello and Prairie 4
Island plants have been fonnalized and documented by the issuance of written directives, procedures and instructions.
The attached Operational Quality Assurance Plan has been written more recently for use as an internal document with a detailed description of the existing QA program, including many references to titles, positions and administrative control directive numbers.
This may require more frequent and extensive revision than a summary description document which would have been prepared for the NRC review process alone.
On the basis that the plan can be revised, as re-quired, through an internal review process, and to avoid preparation of a 1
separate su::raary description, we have chosen to submit the detailed plan for your review needs.
Our operational quality assurance programs have been developed to conform to the requirements of 10CFR50-Appendix B and our Technical Specifications, with heavy reliance upon the guidance and interpretations of ANSI N18.7.
The Regulatory Staff has asked us for commitments to additional documents, particularly Reguistory Guides.
Most of the Regulatory Guides invoke the 9105140459 760930 PDR ADOCK 05000263 P
pyg
s j
NOR..iCRN STATES POWER COMPANY
/.
I D 1. Zicnann 1
Page 2 Sep t embe r 30, 1976
)
guidance of ANSI N45.2 and its series of " daughter standards".
In fact, l
Regulatory Guide 1.33 on Operational Quality Assurance which was issued f
in 1972, referenced both ANS3.2 (later ANSI N18.7-1972) and ANSI N45.2.
I Since the N45.2 series of standards were written mostly for the design and construction of nuclear power plant structures, systems and components, confusion arose among users.
This resulted in the development of ANSI N18.7-1976, which could stand on its own in defining the requirements and recommendations for quality assurance for the operational phase of nuclear i
power plants.
1 i
We believe that our Operational Quality Assurance Plan and its impicmenting i
administrative control directives meet both the requirements of 10CFR50-Appendix B and the objective of having a single consistent set of docu-ments for implementation of the program.
The imposition of commitments to other sets of documents will only lead to confusion for the user, which the revision to ANSI N18. 7 sought to eliminate, and will result in an in-crease in paper rather than meaningful quality assurance.
We believe that the revision of ANSI N18.7 fulfilled its objectives and we endorse it as the singular standard for implementation of 10CFR50-Appendix B l
for operating nucicar plants. This includes !aplementation of the portions of the N45.2 series of standards which ANSI N18.7-1976 references as being applicable for activities during the operational phase.
It would be appro-priate,in our opinion, for the NRC to revise Regulatory Guide 1.33 to adopt ANSI N18. 7-1976 as being an adequate basis for complying with the quality assurance requirements of Appendix B to 10CFR50 and eliminate the multiplicity of references to operational quality assurance in other Regulatory Guides.
Yours very truly,
. G.
w i
L 0 Mayer, PE Funager of Nuclear Support Services i
LCM / deb cc: J G Keppler G Cha rno f f 4
MPCA Attn:
J W Ferman
fe gCoony 195 U S. NVCLE AR AtGUL ATORY CO' S$10N DOCxt t SUMet A 50-263 IJy NRC DISTRIBUTION ron PART 50 DOCKET MATEpl AL
~
F ROMTngp e ogooCvutNT oA To: MR D L ZIE'%?UI MINNFAIOLIS, MINN.......
oaf t MtCtivto 10-4-76 KLtTTim DNoTonizto e m oe iNevironu Nuueta or Corits ntCcivto D omiciN AL UNC L AS$1F lt D l SIGNED tlA(o* Y otSCntPTION ENCLOSURt LTR REF TICHR 6-17-76 LTR, AND THEIR 9-2h-76 REVISION OF OPERATIONAL QUALITY ASSURANCE PLAN GUH tITIAL...... TPANS THE IDLIDWING......
Uru 9-24-76.......
1 b
NOTVzgD Gbh PLANT NAME: % y Q c,g,Q,Q NOT REyoyg SAFETY FOR ACTION /tNFORMATION ENVIRO N
- O N " *lja.JkM ASSIGNED AD:
AS SJ Qg_D_AD r
,s BRANCH CHIEF:
W)
~2IE M AM BRANCH CHTEF*
PROJECT MANACER: /
PROJECI_1ASAGER:
s 6-LIC. ASST. :
QTC. )
' Dis (_cg5 LIC _ ASST INTERNAL DISTRIBUTION (dtEG FT1 r J SYSTEMS SAFET'Y PLANT _.SISIEILS S_ITE ShlETL&
L-NRC PDR HEINEMAN TEDESCO E_NV_IR0_ 6FALY. SIS t,, I&E SCHROEDER BENAROYA DEKIQ R gytf.FR v OELD 1AINAS COSSICK & STAFP ENGINEERING IPPOLITO
. EhXIR0 IECH -
MIPC MACCARRY
};1g};WQOD rpyst CASE KNICHT BALLARD
_JWNA_UER SIHWEIL OPE _ RATING REACT _ ORS S1'ANC1.ER IMRLESS PAVLICKI SIELLO RTTE TECH.
___P_ROJECT_JtAlMG_EMENT REACTOR SAFETY OPERAIll10_IECH.
_GAMMILL h-fLO_Y D ROSS EISEN11tTr STEPP
_ L COLLI.NS NOVAK SHA.O inn 11AN
]
Il0USTON ROSZTOCZY BAER A
PETERSON CHECK pdtfrLER
_ SITE _ ANALYSIS h
MELTZ QiLIMES VOLLMER 1
7 11ELTEMES AT & I
_I)UNCH a
__"'SKOV110LT
_SALTZMAN J,__ COLLINS
- Theit n EE,l2 Gr--
RUTBERC MRPCFR u
EXTERN AL DISTRIBUTION CONTROL NUMBER PLPDR:Sto ti Q @ g /1
_NAT LABL BROOK.UAYENJiALLAIL LSIC:
'73S IC -
la PDR i
v CONSULTANTS ASLn;WC L.R S O_ _..
p....--
~
..__.._.__.__._.___._J_._
1__
.-.---