IR 05000320/1977035

From kanterella
Jump to navigation Jump to search
IE Insp Rept 50-320/77-35 on 770831-0901.No Noncompliance Noted.Major Areas Inspected:Quality Records of Instrument Cable
ML19220B838
Person / Time
Site: Crane Constellation icon.png
Issue date: 09/16/1977
From: Mattia J, Mcgaughy R, Narrow L
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML19220B839 List:
References
50-320-77-35, NUDOCS 7904270450
Download: ML19220B838 (4)


Text

U.S. iiUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No. 77-35 Docket No. 50-320 License No. CPPR-66 Priority

--

Category a

Licensee:

Metropolitan Edison Comoanv Box 542 Reading, Pennsylvania 19603 Facility Name:

Three Mile Island 2 Inspection at:

Middletown, Pennsylvania Inspection condu sed: Au '-t 1-September 1,1977 i

Inspectors:

/ dat6 signed L. Narrow, Reactor Inspector h. C. A%1d 7 [ /l/~7 7 date signed 3. C. Ma ttia, Reactor Inspector date signed Approved by:

0 hl Wh.,

i

/l,!71 Matd si'gned R. M. McGiugIly, Gd'

, Construction Projects Section, RC&ES B ch Insoection Sumary:

Inspection on August 31-Seotember 1,1977 (Recort No. 50-320/77-35)

Areas Inspected:

Routine, unannounced inspection of quality, records of instru-ment cable; and followup on previously reported inspection findings. The inspec-tion involved 24 inspector hours on site by two NRC inspectors.

Results: No items of noncompliance were identified.

(

.

-

Region I Fom 17

(Rev. April 77)

79042704So 83 ^1 T3

-

-

.

DETAILS _

l.

Pers ns Contacted

/r. -ical Licensee Emaioyees i

a.

  • R. F. Fenti, Lead Site QA Auditor
  • R. W. Heward, Manager of Nuclear Projects
  • S. Levin, Project Engineer
  • M. J. Stromberg, Chief Auditor
  • J. E. Wright, Site QA Manager b.

United Enoineers and Constructors, Inc.

  • D. C. Lambert, QC Supervisor c.

Burns & Roe, Inc.

~

  • G. T. Harper, Jr., Site Project Engineer d.

Catalytic, Inc.

,

.

  • J. W. Furlong, Project Engineer

.

  • denotes those present at the exit interview.

The inspector also talked with several other licensee employees as well as employees of the Architect-Engineer and the constructor.

2.

Licensee Action on Previous Inspection Findings (Closed) Unresolved Item (320/77-02-04):

Inconsistencies between

-

the SAR and drawings had been identified in the classification of certain lines in the reactor building spray system and the decay heat removal system.

Arendment 51 to Supplement 2 of the SAR, Sections 21 3/3.2.2 and 21.16/3.2.2 has resolved these inconsis-tencies.

(Closed) Honcompliance (320/77-06-01):

Failure to establish in-spection requirements tur certain purchase orders.

Inspection requirements had been established except for P.O.'s No. 120, 125, 128,164 and 199 (320/77-27). The inspector examined letters from Burns & Roe (B&R) dated August 9, 1977 and August 25, 1977, Serial Nos. 3941-GP and 3955-GP which stated that vendor seismic analysis was not required for the above crders.

The inspector also audited selected items which had been identified as nonconforming for the 1'

lack of documentation on Deviation Report (DR) No. 777 and observed that they had been properly tagged.

-

'

sa ~q

_

i

.

,.

(Closed) Unresolved Item (320/77-27-01):

Apparent incomplete documentation of alignment weld.

The inspector observed that Nuclear Welding Procedure No. 27, " Weld Repair Procedure for Field Welded Piping Systems," had been revised by Field Change No. ti%'-122 to provide for use of this procedure for alignment welds when metal is removed f rcm the original veelds.

This revision identified the applicable section of the procedure #cr alignment welds.

... _

- - _.... _ _ - -

.....

--

---

-

- - - -.

_ -.-- -

- _. _ -

3.

Licensee Internal Audits

.

The inspector examined reports of GPU audit No. 77-13 " Audit of Installation of Penetration Seals," on August 5, 8-11 and 15,1977.

Six findings were identified.

The contractor and licensee management

'

had been notified of these findings by letter dated August 18, 1977.

No items of noncompliance were identified.

4.

OC Records - Instrumentation Cables and Terminations

-

The inspector reviewed QC cable records (receipt inspection, material certifications, installation and termination) to verify that the records reflect work accomplishment in accordance with UE&C Procedure ECP-3-2, Revision 27, titled " Electrical Construction Procedure for Receiving, Storing, Handling and Installing Wire and Cable," and the Burns and Roe cable specifications 255-106 and 255-68.

The following are the cable records reviewed:

Quality Control Material Receiving

-

Cable Circuit Checklist and Certification Report Number Function _

Insoection Report (Company & Date)

Date A.

Reactor Protection., c.n

,

1T2337C Power Range E21109 Anaconda 8/20/76 Detectors E21350 8/13/76 1T2404C Power Range E20845 Anaconda 8/20/76 Detectors E21355 8/13/76 IT2344C Source Range E19592 Anaconda 8/.?0/76 Amplifier E20991 8/13/76 k

-

83 2':S

.

.

.

Receiving Material Quality Control Certi fica tion Report Checklist and Cable Circuit

Inspection Report

(Comoany & Datel

Date

Function

Number

_

Nor-al Plant Control System

1/31/75

B.

Kerite

Reactor Cool-E17794

1/27/75

1T2344C

E19950

ant Flow

1/8/75

Kerite

Reactor Cool-E16278

12/30/74

IT2411C

E19861

nat Flow

1/31/75

Kerite

Reactor Cool-E17795

1/27/75

1T2348C

E19951

Flow

No items of ncncompliance were identified.

plant Tour _

b

5.

The inspector walked through various areas of the plant and o -

t tion

served adherence to QC requirements for housekeep

from previous inspections, particularly on the reactor building

of equipment.

This matter was discussed at the exit

operating floor level.

interview.

No items of noncompliance were identified.

Review of Nonroutine Events Reported by the t.icensee_

6.

the licensee had reported as a significant

l

f

deficiency in accordance with 10 CFR 50.55(e), that, as a res

-

On March 14, 1977,

l skirt, the

pressure losses in the duct work to the reactor vesse l

design basis temperature of 150* F in the concrete reactor ves

ilation

support structure could not be maintained by the

The

of equipment to supply additional air flow pa

-

system.

h

Category I,

tha nonral ventilation system was classified a

l information

B&R.

to support this position would be made available by

This item remains unresolved.

Exit Interview

7.

Para-

The inspector met with licensee representatives (denoted in

b

1, 1977.

graph 1) at the conclusion of the inspection on Septem er

i

The inspector surm:arized the scope and findings of the ins

-

/

The licensee representatives had no coments.

l

'

-

[qq 4,. -

+. A. D

_._

-