ML19326D187
| ML19326D187 | |
| Person / Time | |
|---|---|
| Site: | Midland |
| Issue date: | 02/05/1976 |
| From: | Bauman R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Boyd R Office of Nuclear Reactor Regulation |
| References | |
| 2133, NUDOCS 8006090612 | |
| Download: ML19326D187 (5) | |
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\\2y < f' bulliyLiiij Ns General Omces: 212 West Michigan Avenue, Jackson, Micnigan 49201. Area Code 517788-0550 February 5, 1976 Director of Nuclear Reactor Regulation
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T Attention:
Mr. Roger Boyd, Director inj0fj
. ;g Division of Project Management gg g" Y "'y U.S. Nuclear Regulatory Commission i
Washington, DC 20555 N
ak MIDLAND PROJECT
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DOCKET NUMBERS 50-329, 50-330 y
REGULATORY GUIDE IMPLDENTATION FILE: 0505 SERIAL:
2133 The enclosed information partially responds to Mr. A. Schwencer's January 26, 1976 letter requesting additional information on implementation of Regulatory Guides relative to quality group, seismic classifications and concrete placement.
Responses to questions on Regulatory Guides 1.26 and 1.29 are transmitted herewith.
The response on Regulatory Guide 1.94 will be submitted by February 11, 1976.
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R. C. Bauman Project Engineer A-
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i 211.1 Figure 4.1-1 of Amendment 26'to the PSAR indicated that the feedwater ring header has been constructed.to the ANSI Power Piping Code Bal.1.0.
This component was purchased in 1968 and thus predates current regulatory requirements which' i
requires construction to ASME Section III, Class 2.
In order to assure an acceptable level of quality for this component, identify the non-destructive examinations performed on the welds of the ring header.
Response
i Welds and associated non-destructive examinations of the ring headers are classified in two categories; shop welds and j
examinations or field welds and examinations.
a.
Shop procedures:
1.
Header-to-end-cap welds were non-destructively examined both radiographically and by magnetic particle test.
2.
Riser stub-to-header welds were examined by magnetic particle test only.
I 3.
Header-to-tee welds were examined radiographically and by magnetic particle test.
b.
Field procedures:
1.
All field welds and inspections of welds will be to standards defined in the ASME Code,Section III, 1971 edition, including Addenda through the summer of 1973.
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O 211.2 Identify those portions of the Makeup and Purification System that provide seal injection cooling water to the reactor coolant pumps and are constructed to ASME Section III, Class 3 and Seismic Category I requirements.
Response
The following schematic diagram shows the piping class configuration of the seal injection system:
NORMAL MAZEUP courAruesar h
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Hl6H PCE.99tJEn g g g g g g IWECI'lOM RJMP9
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MAINTENANCE 190LATCM VALVES 1 - ASME Section III Class 1 and Seismic Category I 2 - ASME Section III Class 2 and Seismic Category I 3 - ASME Section III Class 3 and Seismic Category I 2
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211.3 Identify those valves in fluid systems important to safety that you classify as remote manual" and are not in conformance with position C.l.d in Regulatory Guide 1.26.
Identify each valve by valve number and the appropriate Piping and Instrumentation diagram on-which it is shown.
Response
The valves in the steam and feedwater systems will be in conformance with Regulatory Guide 1.26 Position C.l.d.
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q NRC Dio. AIBUTIOJj_F_OR PART 50 DOCKET. 4TERI AL (TEMPOR..ARY FORM)
CONTROL NO: 124O FILE:
FROM: Consumers Pwr Co DATE OF DOC DATE REC'D LTR TWX RPT OTHER Jackson, Michigan 2-5-76 2-9-76 XXXX R C Batiman TO:
ORIG CC OTHER
. SENT!CC PDR XX SENT LOCAL PDR XX CLASS UNCLASS PROPINFO INPUT NO CYS REC'D DOCKET NO:
@ 30 XXXXXXX 1
DESCRIPTION:
ENCLOSURES:
~Ltr re our 1-26-70 ltr...trans the following:
Addl linfo concerning implementation of
~~
Reg Guides concerning quality group,- seiskmic classifications & concrete placement.........
(10 cys encl rec'd)
PLANT NAME:
Midland 1 & 2 SAFETY FOR ACTION /INFC P3AATION y,,n,o 9_1 n u ec ASSIGN":.D AD ASSICEED PRANCH CHIEF
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PROJECT MANAGER PROJECT MANAGER LIC ASST.
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CYS ACRS INTERNAL DISTRIBUTION FI}E d SYSTEMS SAFETY PLANT SYSTEMS SITE SAFETY & ENVIT;0 ANALYSTS y
NRC PDR HEINEM/W TEDESCO DENTON MULI.ER f
OELD SCHROEDER BENAROYA GOSSICK/ STAFF LAIN A.S ENV1R0 TECil.
SITE ANALYSIS IEE (2)
ENGINEERING IPPOLITO ERNST VOLLMER
/ M1PC MACCARY Ki e E u c' BALLARD BUNCH KNICHT
' OPERATING RE ACTORS SPANGLER J. COLLINS CASE PROJECT MANAGEMErr SIINEIL STELLO KREGER j
E0YD PAULICKI.
SIT 11 TECH.
P. COLLINS A * / / " #/
OPERATING TECH.
GAMMILL.
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11C STON REACTOR SAFETY _
EISENiiUT STEPP SALTZMAN PETERSON ROSS SHA0 HULM!.N RUTBERG MELTZ NOVAR BAER HELTEMES ROSZTOCZY SCHUENCER MISCELLANEOUS CHECK GRIMES g,g,c c
EXTEr<NAL DISTRIBUTION LOCAL PDR /21, d In n /
,73 NATIONAL LAB _
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CYS BRC0KHAVEN NAT. LAB i
f TIC REGION '.*-I&E-(WALNUT CREEK)
ULRIKSON (ORFL)