ML18005A374

Responds to NRC Re Violations Noted in Insp Rept 50-400/87-41.Corrective Actions:Further Calculations Done. Three Personnel Involved W/Subj Calculations No Longer Involved in Design Activities

ML18005A374
Person / Time
Site:	Harris
Issue date:	03/24/1988
From:	Watson R CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
CON-NRC-615 HO-880082-(O), NUDOCS 8803310212
Download: ML18005A374 (6)

Text

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS>

ACCESSlON NBR: 8803310212 DOC. DATE: 88/03/24 NOTARIZED:

NO DOCKET

~'FACIL: 50-400 Shearon Harris Nuclear Poeer Plant'nit ii Carolina 05000400 AUTH. NAME AUTHOR AFFILIATION MATSQNi R. A.

Carolina Power 5 Light Co.

REC IP. NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Responds to NRC 880225 ltr re violations noted in Insp Rept 50-400/87-41. Corrective actions:further calculations done.

Three of per sonnel involved e/sub'alculations no longer involved in design activities.

DISTRIBUTION CODE:

IE01D COPIES RECEIVED: LTR ENCL SIZE:

TITLE: General (50 Dkt>-Insp Rept/Notice of Violation Response NOTES: Application for permit reneeal filed.

05000400 INTERNAL:

REC IP IENT ID CODE/NAME PD2-1 PD ACRS DEDRO NRR/DLPG/PEB11B NRR/DOE* DIR11E NRR/DREP /RP 8 10A NRR/PMAS/ ILRB12 OGC 15-B-18 RES/DRPS DIR COPIES LTTR ENCL 1

1 P

2 1

1 1

1 1

2 2

1 1

1 1

1 1

RECIPIENT ID CODE/NAME BUCKLEYiB AEQD NRR MORISSEAUz D NRR/DLPG/GAB10A NRR/DREP /EPB 10D NRR/DR IS DIR9A2 O~~BERMANiJ REG FILE 02 RGN2 'FILE 01 COPIES LTTR ENCL 2

2 i

i.

1 1

1 1

1 1

1 1

1 1

1 1

1 EXTERNAL:

LPDR NSIC 1

1 1

1 NRC PDR 1'

e TOTAL NUMBER QF COPIES REQUIRED:

LTTR 24 ENCL 24

CHAL Carolina Power & Light Company HARRIS NUCLEAR PROJECT PE 0.

Box 165 New Hill, North Carolina 27562 NAR 24 1988 File Number'SHF/10-13510E Letter Number:

HO-880082 (0)

NRC-615 Document Control Desk United States Nuclear Regulatory Commission Washington, DC 20555 r

r SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50"400 LICENSE NO. NPF-63 REPLY TO A NOTICE OF VIOLATION Gentlemen:

In reference to your letter of February 25, 1988 referring to I.E.

Report RII:

50-400/87-41, the attached is Carolina Power

& Light Company's reply to the violation identified in Enclosure 1.

It is considered that the corrective actions taken are satisfactory for resolution of the item.

Thank you for your consideration in this matter.

Very truly yours, R. A. Watson Vice President Harris Nuclear Project MGW:mdt Attachment cc'Messrs.

B. C. Buckley (NRC)

G. Maxwell (NRC-SHNPP) e Dr. J. Nelson Grace (NRC) 8803310212 880324 PDR ADOCK. 05000400 6

PDR MEM/HO-8800820/1/OS1

Attachment to CP&L Letter of

Response

to 'NRC I.E.

Report RII:

50-400/87-41 Re orted Violation.'0 CFR 50, Appendix B, Criteria III, as implemented by the CPGL accepted QA program (FSAR Chapter 17.2) requires that changes to design inputs be identified, approved, documented and controlled.

Contrary to, the

above, the design input for the change in temperature (AT) value used in evaluating thermal stresses in the containment building riser structure in calculation LV-66 was changed from 148'F to 60'F.

The value of AT = 148'F was the design input value based on DBA temperature, used in calculation of thermal stresses affecting reactor building steel structures.

The reasons for change to this design input was not identified, and the change was not

approved, documented or controlled.

As a

result, calculation LV-66 required revisions to incorporate the correct design input value for AT of 148'.

r This is a Severity Level IV violation (Supplement II).

Denial or Admission and Reason for The Violation'.

The violation is correct as stated.

The design input utilized for the Containment Building Riser Structure was revised from a

AT of 148'o 60'ased upon the assumption that the overstress of the steel due to thermal load while the plant is in a

nonoperative mode following a DBA was inconsequential.

However, the correct AT to be used in the thermal portion of the analysis is 148'.

Corrective Ste s Taken and Results Achieved:

Further calculations have been done.

Using corrected thermal values and allowable stresses

(

Reference:

NCR 87-151),

the additional calculations determined containment cable tray risers were acceptable with no additional field work required.

Corrective Ste s Taken to Avoid Further Noncom liance'.

The two Design Engineers and the supervisor involved with the subject calculations are no longer involved in design activities for the Harris Plant.

However, one of the designers is still employed by CPSL in a contract capacity and has been counseled in the proper documentation and control of design inputs per

10CFR50, Appendix B, Criterion III.

HEN/HO-8800820/2/OS1

, The control of the structural design activities has been moved to the Nuclear Engineering Department (NED),

Central Design Organization.

Work for the Harris Plant by NED is performed under HPES Manual of Instruction in which Section 3.29 has been established to expand and reinforce the engineer,

checker, design

verifier, and supervisor relationship discussed in

10CFR50, Appendix B,

Criterion III.

Individuals involved with future modifications to these structures have been instructed in the proper use of thermal loading required for design.

Further, NED personnel have been additionally trained and are aware of 10CFR50 Appendix B,

Criterion III requirements for control and documentation of design inputs.

Date When Full Com liance Was Achieved:

Full compliance was achie'ved on March 15, 1988.

MEM/HO-8800820/3/OS1