IR 05000329/1978014

From kanterella
Jump to navigation Jump to search
IE Inspec Repts 50-329/78-14 & 50-330/78-14 on 780910-29 During Which No Items of Noncompliance Were Noted.Major Areas Inspected Incl:Examination of Gen Site Condition & Steam Generator & Reactor Vessel Hold Down Bolting
ML20062F096
Person / Time
Site: Midland
Issue date: 11/06/1978
From: Cook R, Hayes D
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20062F084 List:
References
50-329-78-14, 50-330-78-14, NUDOCS 7812140139
Download: ML20062F096 (4)


Text

.

'.

.

..

.

.

U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT

, REGION III

.

. Report No. 50-329/78-14; 50-330/78-14 Docket No. 50-329; 50-330 License No. CPPR-81, CPPR-82 Licensee: Consumers Power Company

'

1945 West Parnall Road Jackson, MI 49201 Facility Name: Midland Nuclear Power Plant, Units 1 and 2 ,

Inspection At: Midland Site, Midland, MI Inspection Conducted: Sep mber 10-29,1978

'

I ! Inspector: R. J Cook c

[

<< r Approved by: D. W. Hayes, Ch 8 Projects Section /'

~

s Inspection Summary Inspection on September 10-29, 1978 (Report No. 50-329/78-14; 50-330/78-14) '

Areas Inspected: Examination of the general site condition, steam generator;

~

and reactor vessel hold down bolting, auxiliary piping system field welding s

, and fabrication, status of repair to the 1.p. turbine rotors, settlement of the diesel generator foundations and structures, erection of Unit 2

-

reactor coolant system piping, welding on Unit 2 core flood system piping, '

, review of NDE procedures used by B&W Construction Company, in place storage condition of electrical equipment, information meetings with licensee personnel. This inspection effort involved a total of 71 inspection-hours by one NRC inspecto Results: No items of noncompliance or deviations'were identifie %

.

e 781214 O( 3,g

.

\

-

- l

. ..

. \

l i

. ,

-

.

-

DETAILS ,

! Persons Contacted D. Miller, Site Manager 1, T. Cooke, Project Superintendent

  • J. Corley, Project QA Superintendent B. Marguglio, Manager, Quality Assurance W. Bird, Section Head, Quality Engineering
  • L. Dreisbach, Bechtel Corporation Project Field QA Engineer
  • R. Shope, B&W Project Engineer Numerous other principal staff and personnel were contacted during the reporting perio ,

'

  • denotes those present at the exit intervie Inspection Areas

-> Site Tours .

At periodic intervals generalized tours of the facility were per-formed by the Resident Inspector. These tours covered essentially all areas of the site. The tours were intended to assess the cleanliness of the site; construction activities in progress; storage condition of equipment and piping used in site construction; and the potential for fire or other hazards which might have a ,

dilaterious affect on personnel and equipmen It was noted during these tours that temporary lay down areas for safety related piping were starting to deteriorate. This was brough to the licensee's attention and immediate steps were taken to upgrade the temporary '

-

lay down area . Steam Generator and Reactor Vessel Hold Down_ Bolting i

'

Open (Item No. 329/78-13-02; 330/78-13-02) - The procedure for i setting the reactor vessel and steam generator hold down bolts i

has not yet been completely finalized and accepted. However, the licensee indicated that tensioners may be used to establish the required bolting preload.

. Auxiliary Piping System Field Welding and Fabrication

'

Field fabrication of piping being installed in the Auxiliary building was examined. This included witnessing veld preperation, fit up and

,

'

. welding of piping joints in the decay heat removal and make up feed systems and other system joints welded in the auxiliary building. It I .

, -2-

.

-

. _ _ _ _ _ _ . _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ __

.

.

.

. .

.

.

appeared that controlled rod withdrawals were being made per procedure Nos. WFMC-1 and F1W-1.120. The licensee is determinin'g the need to establish the times of subsequent rod withdrawals made during a y, given shif t against a given authorization for rod withdrawal i' (W-6 or WR-6 Form).

o L. P. Turbine Damage I The licensee has informed the inspector that the latest estimate of shipping the L. P. turbines damaged in a train derailment, is mid-year 1979. At this time there is no known impact on overall plant scheduling.

l .55(e) Item

,

Settlement of Diesel Generator Foundations and Structure _

,

Open (Item No. 329/78-13-03; 330/78-13-03) - The licensee has kept the Resident Inspector informed of exploratory activities associated with evaluations pertaining to the settling of the diesel generator /.

-

, building foundations and structures. Approximately 100 core horings i have been or will be extracted from various locations around the site and diesel building for further evaluation by an independent labora-tory. Relative soil density measurements have been taken at three i locations to further enhance the evaluations pertinent to the diesel -!

building settlement. An escalated survey program has been put into affect to monitor the rate of settlemen ;

steam generator. The inspector examined fit up of other portions of

. the Unit 2 reactor coolant piping which is presently being installe ,

,

The inspector witnessed B&W Construction Company QC perform an examination of the Weld preperation for the Unit 2 reactor coolant system hot leg piping for the B-steam generato ]

. (x l Core Flood Line Unit 2 -l l

The inspector witnessed welding operations of Field Weld Number 14 on spool 2CCA-21-S-611-1-2 for the core flood system of Unit 2 located at the 606 foot elevation and examined weld preperations on adjacent piping. No deviations or items of noncompliance were observe . B&W Construction Company NDE

.

The Resident Inspector assisted K. Ward, Reactor Inspector, RIII in ,

the evaluation of procedures intended for NDE use by B&W Construction Company. The licenst e also has an active NDE procedure review progra > -2-

'

.

W + ,

Y s -

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

.

-

.

-

. Inplace Storage of Electrical Equipment Inplace 9torage of electrical equipment in proximity to the control

,. room var. examined during the reporting period. The equipment appeared l to be T-operly protected from weathering condition ,

1 Licensee Meeting The Resident Inspector met at various times with licensee principal staff members from the corporate QA group and the Operations Group located onsite. These meetings were for the exchange of information which may assist the licensee in developing their programs to meet future regulatory requirements and to alert the licensee to events at other sites which may have an affect on the Midland Plan I Exit Interview ,

The Resident Inspector attended the Exit Interview conducted by I. Yin and K. Ward, RIII Reactor Inspectors on September 15 and September 28, 1978, respectivel /,.

The Resident Inspector met with licensee representatives (denoted nder Persons Contacted) on September 20, 1978. The inspector summarized the scope and findings of the inspection effort to date. The licensee acknowledged the findings reported herei '

.

i l

t

?

?

l

.

-4-

.

V

'"_ . * ,

- - - - - - - - - - _ - _ _ _ _ . _ . - . _ .