ML20236H731

Interim Deficiency Rept CP-86-19 Re Installation of Steam Svc Pressure Transmitters.Initially Reported on 860321. Engineering Developing Design Mod Package (DM-86-140) Re Unit 1 Instrument Installations.Next Rept by 871202

ML20236H731
Person / Time
Site:	Comanche Peak
Issue date:	07/30/1987
From:	Counsil W, Keeley G TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
CP-86-19, TXX-6606, NUDOCS 8708050315
Download: ML20236H731 (3)

Text

_ .

Log # TXX-6606 File # 10110 910.3

== Ref # 10CFR50.55(e)

~

.- =

TUELECTRIC 0"'Y O' I98l William G. Counsil hecutwe nt Prrudent U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mashington, D. C. 20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) l DOCKET NOS. 50-445 AND 50-446 j INSTRUMENTATION INSTALLATIONS l i SDAR: CP-86-19 (INTERIM REPORT) l  !

l l Gentlemen: I l l On March 21, 1986, we notified you of a reportable item involving the j installation of steam service pressure transmitters (see TXX-4824 dated May 23,1986). This is a follow-up interim report to status the corrective actions for a reportable item under the provisions of 10CFR50.55(e). Our last I interim report was logged TXX-6332 dated March 20, 1987.

]

1

The scope of this item has been expanded to include corrective action j implementation for SDARS

CP-86-16, " Fire Effects on Instrument Tubing," CP- J 86-50, "Unistrut Spring Nuts on Instrument Supports," CP-86-70, " Elevated  ;

Temperature Effects on Instrument Supports and Tubing," and CP-86-77, J

" Instrument Tubing Minimum Wall Thickness"; all of which were previously l reported under the provisions of 10CFR50.55(e).

SDAR CP-86-16: FIRE EFFECTS ON INSTRUMENT TUBING Engineering evaluation of this issue is continuing; corrective actions have yet to be defined.

SDAR CP-86 '9: INSTRUMENTS MOUNTED ABCVE PROCESS TAPS l Engineering is developing the design modification package (DM-86-140) required to modify the Unit 1 instrument installations. This design modification will involve relocating the instruments to an elevation below the root valves and rerouting the tubing to the proper slope requirements as defined in Specification CPES-I-1018. Unit 2 instruments will be corrected similarly to Unit 1.

8708050315 870730 A PDR ADOCK 05000445 S PDR (f I

4tu North Obvc Street i.B 81 Dallas. Texas 75201 L_______---_-_____

i

. l TXX-6606  ;

July 30, 1987  !

Page 2 of 3  !

l SDAR CP-86-50: UNISTRUT SPRING NUTS ON INSTRUMENT SUPPORTS 1 i

The following is the corrective action plan for this issue. )

1) Construction shall revise the installation procedures to reflect the new criteria (torque and alignment) as defined in Specification CPES-I-1018.

2) Construction personnel will be trained in the new criteria.

l l 3) Quality Control shall revise the inspection procedures to reflect I the new criteria as defined in Specification CPES-I-1018. '

4) Quality Control personnel will be trained to the revised procedures.

5) Construction personnel shall rework 100% of the installations to conform to the new criteria with Quality Control inspection personnel providing verification and documentation of torque and spring nut alignment.

SDAR CP-86-70: ELEVATED TEMPERATURE EFFECTS ON TUBING AND SUPPORTS l Engineering has reviewed and evaluated calculation number 304, Rev.1, " Review of Accident Elevated Temperature Effects on Tubing," and concludes that any  ;

additional loads due to accident conditions are included in the tubing support criteria. The calculation incorporates strain criteria as suggested in NUREG 1061, " Report of the US NRC Piping Review Committee," Volume 2, Section 2.5.

Safety-related instruments and non-safety related instruments connected to ASME III fluid systems and ANSI safety class installations associated with CPSES Unit I and 2 as defined by field verification method CPE-FVM-IC-069 are being evaluated in accordance with this criteria.

SDAR CP-86-77: INSTRUMENT TVBING MINIMUM WALL THICKNESS The following is our corrective action plan for this issue.

1) The minimum wall thickness of 0.035 inches has been determined to be acceptable for 3/8 inch 0.D. stainless steel tubing in all applications.

2) Quality Control shall revise the inspection procedures to reflect the new criteria provided in Specification CPES-I-1018 for all 1/2 inch 0.D. stainless steel tubing installed as impulse lines in the reactor coolant, chemical and volume control, and safety injection systems.

3) Inspection personnel will be trained in accordance with the revised procedure.

4) QC will perform 100% reinspection per revised procedure and document all deficiencies via NCRs.

l

TXX-6606- ,

July.30, 1987 j Page 3 of 3 .j t

5) Engineering ~will evaluate each deficiency and disposition the NCR.

It is anticipated that rework will be required of any deficiencies-found in the reactor coolant system tubing. Chemical and volume control system and safety injection system deficiencies will be evaluated with due consideration for actual pressure / temperature [

exposure.

-l

6) Construction shall revise the existing procedure to reflect the new criteria of Specification CPES-I-1018. i 1

-7) Construction personnel will be trained in accordance with the revised procedure.

.{

8) Construction will rework the deficiencies as directed by -.

Engineering to conform to Specification CPES-I-1018.

9) Rework will be reinspected for-compliance to the revised .

procedure. I Engineering Calculation #16345/6-IC-(B)-001 was prepared to determine the maximum pressure / temperature conditions which 0.035 inch thick. wall stainless steel tubing may be exposed. This calculation determined the minimum wall thickness required for the maximum pressure / temperature anticipated at CPSES.

The criteria derived and based on this calculation has been incorporated into Specification CPES-I-1018. l Engineering evaluations of SDAR CP-86-16 and CP-86-70 are ongoing. Resolution '

and corrective actions are scheduled to be completed by October 30, 1987. 1 1

Our next report will be submitted by December 2, 1987. l Very truly yours, W. G. Counsil l By: . .

s /

G. S. Keele<y~ L Manager,Nucleayicensing GLB/gj c - Mr. R. D. Martin, Region IV  !

Resident Inspectors, CPSES (3) l

!