ML19332C640

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Forwards Insp Repts 50-445/89-79 & 50-446/89-79 on 891016- 27.No Violations or Deviations Noted.Actions Taken to Clarify Auxiliary Feedwater Test Data Package & on Any Other Packages Requested within 30 Days
ML19332C640
Person / Time
Site: Comanche Peak  Luminant icon.png
Issue date: 11/20/1989
From: Girmes C
Office of Nuclear Reactor Regulation
To: William Cahill
TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
Shared Package
ML19332C641 List:
References
NUDOCS 8911280376
Download: ML19332C640 (8)


See also: IR 05000445/1989079

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This refers to the inspection conducted by Messrs. M.-E. Murphy and R. V. Azua

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of this office during the period October 16i27, 1989, of activities authorized

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by,NRC Construction Permits CPPR-126 and CPPR-127 for Comanche Peak Steam Electric

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Station Units 1 and 2, and to the discussion oflour findings with Mr. H. D. Bruner

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and other members of your staff at the conclusion of the inspection.

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Areas' examined during the inspection included preoperational test results

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evaluation and review of the containment integrated leak rate test results.

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,Within these areas, the inspection consi:ted of selective examination of

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procedures and representative records, interviews with personnel,.and

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. observations by the inspectors. The inspection findings are documented in the

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Within'the scope of the inspection, no violations or deviations were

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identified.

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During-this inspection..it was determined that the test data package for the

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auxiliary feedwater (AFW) system was not sufficiently clear-and it appeared

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adequately explained from discussions with personnel involved in the test;

however, this has created a concern over the clarity and continuity of the' test

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within 30 days of the date of this inspection report. Your response should

include the actions taken to clarify the AFW test data package and your actions

taken, or to be taken to identify and clarify'any other test data packages.

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This response should specifically address the adequacy of the joint test group

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Should you have' any questions concerning this inspection, we will be pleased to .

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Sincerely,

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Office of Nuclear Reactor Regulation :

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Enclosure: '

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' Appendix - NRC-Inspection Report-

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ATTN:

W. J. Cahill, Jr., Executive

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Vice President, Nuclear

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400 North Olive

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. This refers to the inspection conducted by Messrs. M. E. Murphy and R. V. Azua

'of this office during the period October 16-27, 1989, of activities authorized

by NRC Construction Pemits CPPR-126 and CPPR-127 for Comanche Peak Steam Electric

Station Units 1 and 2, and to the discussion of our findings with Mr.

H.= D. Bruner

.and other members of your staff at the conclusion of the inspection.

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Areas examined during the inspection included preoperational test results

evaluation and review of the containment integrated leak rate. test results.

Within these areas, the inspection consisted of selective examination of

procedures and representative records, interviews with personnel, and

observations by the inspectors. The inspection findings are documented in the

enclosed inspection report.

Within the ' scope of the inspection, no violations or deviations were

tidentified.

'

During this inspection it was determined that the test data package for the

. auxiliary feedwater (AFW) system was not sufficiently clear and it appeared

'that one of the test acceptance criteria was r.ot met. This condition was

adequately explained from discussions with personnel involved in the test;

however, this has created a concern over the clarity and continuity of the test

data packages similar to our previous concerns over the cold hydrostatic test

data._ You are requested to respond to this concern, in writing, within 30 days

of the date of this inspection report. Your response should include the

actions taken to clarify the AFW test data package and your actions taken, or

to be taken to identify and clarify any other test data packages. This response

should specifically. address the adequacy of the joint test group reviews.

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-Dockets: 50-445/89-79

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ATTN: ,-W. J. Cahill

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Vice President Nuclear

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' This refers to the inspection conducted'by Messrs. 'M. E. Murphy and R. V. Azua

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of this office during the period October 16-27. 1989, of activities authorized

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by'NRC Construction Pemit CPPR-126 for Comanche Peak Steam Electric Station,

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Unit 1 and to the' discussion of our findings with Mr. H. D. Bruner and other.

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members of your staff at the conclusion of the inspection.

-

Areas examined during the inspection included preoperational test results

i

evaluation and review of the containment integrated leak rate test results.

!

Within these arecs, the inspection consisted of selective examination of

i

procedures anG. representative records, interviews with personnel, and

observations by the inspectors. The inspection findings are documented in the

enclosed inspection report.

,

,

4 Within the scope of the inspection, no violations or deviations were

identified.

't

.During this inspection, it was determined that the test data package for the

. auxiliary feedwater (AFW) system was not sufficiently clear and it appeared

'

that one of the test acceptance criteria was not. met. This condition was

adequately explained from discussions with personnel _ involved in the test;

i

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however.'this has created a concern over the clarity and continuity of the test

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data packages similar to our previous concerns over the cold hydrostatic test

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data. You are requested to respond to this concern, in writing, within 30 days

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'of the date of this inspection report. -Your response should include the-

actions taken to clarify the AFW test data package and your ections taken, or

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to be taken to identify and clarify any other test data packages. This response

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50-445/89-79; 50-446/89-79'

DISTRIBUTION:

Docket File (50-445/446)

NRC PDR

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ADSP. Reading

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J. Gilliland, RIV

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Shea, ARM /LFMB

C. I. Grimes

J. H. Wilson

J. Lyons

'M. Mal.loy

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J. Moore, OGC

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D. Crutchfield

T. Quay

E. Jordan

B. Grimes-

B. Hayes

C. Vandenburgh

J. Partlow

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NUCLEAR CEGULATORY COMMISSION

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REGION IV

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ARLINGTON. TEXAS 70011 -

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NOV 2 01989

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In Reply Refer To:

Dockets:

50-445/89-79

50-446/89-79

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TU Electric

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ATTN:

W. J. Cahill, Jr.. Executive

Vice President. Nuclear

Skyway Tower

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400 North Olive. L.B. 81

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Dallas, Texas 75201

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Gentlemen:

This refers to the inspection conducted by Messrs. M. E. Murphy and R. V. Azua

3

of this office during the period October 16-27, 1989, of activities authorized

?

by NRC Construction Permits CPPR-126 and CDPR-127 for Comanche Peak Steam Electric

Station, Units 1 and 2. and to the discussion of our findings with Mr. H. D. Bruner

and other members of your staff at the conclusion of the inspection.

!

Areas examined during the inspection included preeperational test results

'

evaluation and review of the containment integrated leak rate test results.

Within these areas, the inspection consisted of selective examination of

procedures and representative records, interviews with personnel, and

'

observations by the inspectors. The inspection findings are documented in the

'

enclosed inspection report.

Within che scope of the inspection, no violations or deviations were

identified.

.

During this inspection, it was determined that the test data package for the

auxiliary feedwater (AFW) system was not sufficiently clear and it appeared

that one of the test acceptance criteria was not met. This condition was

adequately explained from discussions with personnel involved in the test;

however, this has created a concern over the clarity and continuity of the test

data packages. You are requested to respond to this concern, in writing,

within 30 days of the date of this inspection report. Your response should

i

include the actions taken to clarify the AFW test data package and your actions

taken, or to be taken to identify and clarify any other test data packages.

This response should specifically address the adequacy of the joint test group

.

'

reviews.

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Should you have any questions concerning this inspection, we will be pleased to

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discuss them with you.

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Sincerely,

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C. I. Grimes Director

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Comanche Peak Project Division

Office of Nuclear. Reactor Regulation

Enclosure:

Appendix - NRC Inspection Report

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50-445/89-79 w/ attachment

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50-446/B9-79 w/ attachment

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W'. J.-Cohill, Jr.

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NOV 201989

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Roger D. Walker

TU Electric

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Manager, Nuclear Licensing

c/o Bethesda Licensing

TU Electric

3 Metro Center, Suite 610

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Skyway Tower

Bethesda, Maryland- 20814

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400 North Olive Street', L.B. 81

Dallas, TX

75201

E. F. Ottney

P. O. Box 1777

Juanita-Ellis

Glen Rose, Texas

76043

,

President - CASE

'

1426 South Polk Street

Jack R. Newman

Dallas, TX

75224

Newman & Holtzinger

.

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1615 L Street, NW

Texas Radiation. Control

Suite 1000

'

Program Director

Washington, DC' 20036

Texas Department of Health

1100 West 49th Street

George R. Bynog

Austin, Texas

78756

Program Mgr./ Chief Inspector

Texas Dept. of Labor & Standards

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GDS Associates, Inc.

Boiler Division

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1850 Parkway Place,-Suite 720

P.O. Box 12157, Capitol Station

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Marietta, GA

30067-8237

Austin, Texas

78711

,

Honorable George Crump

County Judge

Glen Rose, Texas

76043

Ms. Billie Pirner Garde, Esq.

'

Robinson, Robinson, et al.

103 East College Avenue

Appleton, WI

54911

Regional Administrator, Region IV

U.S. Nuclear Regulatory Commission

'

611 Ryan Plaza Drive, Suite 1000

Arlington, Texas

76011

William A. Burchette, Esq.

Counsel for Tex-La Electric

Cooperative of Texas

Heron, Burchette, Ruckert & Rothwell

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1025 Thomas Jefferson St., NW

Washington, DC

20007

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