IR 05000498/1985008

Insp Repts 50-498/85-08 & 50-499/85-08 on 850501-0630.No Violation or Deviation Noted.Major Areas Inspected:Site Tours,Licensee Action on Previously Identified Items,Plant maint,in-place Protection of Equipment & Operator Training

ML20136E661
Person / Time
Site:	South Texas
Issue date:	12/23/1985
From:	Carpenter D, Constable G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20136E652	List: IR 05000498/1985008 ML20136E648
References
50-498-85-08, 50-498-85-8, 50-499-85-08, 50-499-85-8, NUDOCS 8601070091
Download: ML20136E661 (6)

Text

- _____ ____ _ _ _ __

e

'

. . . . .

,. + .

-

APPENDIX

.

'

U. S. NUCLEAR. REGULATORY COMMISSION

REGION IV

,

NRC Inspection Report: 50-498/85-08 Construction Permits: CPPR-128 and 50-499/85-08 CPPR-129 s Dockets: 150-498-50-499 ' e-

Licensee:. Ho w ton Lighting & Power Company (HL&P)

P. O. Box 1700

-

Houston, Texas 7700 I South Texas Project, Units 1 and 2 Facility Name:

Inspection At:. South Texas Project, Matagorda County, Texas Inspection Conducted: May 1 - June 30, 1985 Inspector: /2//MD'

D.1.'- C/rpenter, Resident Inspector Datel

'

'

W

'

E. E. Constable Chief- Date '

Project Section C Reactor Projects Branch

-

Inspection Summary c nducted May 1 - June 30, 1985 (Report 50-498/85-08; Areas Inspected: Routine, unannounced inspection included site tours, licensee action on previously identified items, plant maintenance, inplace protection of equipment, operator training and simulator and startup activitie The inspection involved 157 inspection onsite hours by one NRC inspecto Results: Within the scope of this inspection, no violations or deviations were identifie One new unresolved item was identified and is discussed in paragraph {DR ADOCK 05000498 PDR

-6 's A L

,

-2-

,

DETAILS Persons Contacted Principal Licensee Employees R. Balcom, Reactor Operations Supervisor ~ '

- J. Hughes, Castruction Superintendent D. Cody, Training Manager

• R. Daly, Startup Manager

• S. Dew, Deputy Project Manager

• J. Goldberg, Vice President, Nuclear

• J. Green, Operations QA Manager T. Jordan, Site QA Manager

• W. Kinsey, Plant Manager M. Ludwig, Maintenance Manager

• ft. McDurnett, Licensing Supervisor A. Peterson, Startup Engineer Special Projects

• J. Westermeier, Project Manager

• F. White, Site Licensing

• J. Williams, Site Manager

• B. Franta, Manager, Staff Training

• R. Hernandez, Manager, Project Compliance Other Personnel '

Bechtel . Power Corporation (Bechtel)

• R. Medina, Lead QA Engineer

• L.' Hurst, Project QA Manager A. Priest, Site fianager Ebasco Services, Inc. (Ebasco)

• A. Cutrona, Quality Program Site Manager

• J. Thompson, Site Manager Westinghouse Electric Company (Westinghouse)

• A. Hograth, Site Manager The NRC inspector also interviewed additional licensee personnel, Bechtel personnel, and other contractor personnel during this inspectio * Denotes those individuals attending one or more exit meetings during the inspection perio .-- - - _ _ _

. .-

-3- Site Tours During this reporting period, routine tours of the site were conducted by the NRC inspector to observe ongoing work activitie The general plant cleanliness was acceptable. Areas of concern were noted to the licensee. Plant cleanliness at South Texas Project (STP)

appears to be steadily improving. Continued attention needs to be paid to areas off the beaten pat General construction activities and prerequisite testing activities were observed in Unit 1 NEAB, Diesel Generator Building, Fuel Handling Building, Reactor Containment Building, and 80P support facilities. For Unit 2, no testing activities were observe '

The Unit 1 control room is manned 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day by shift operations personnel. There was a small fire under Unit 1 Reactor Vessel and neither the control room nor operations were notified, nor were they aware of the fire the following day. This fire was considered a construction problem, not operations, but operations does perform around-the-clock plant tour This was discussed with the plant manager and deputy project manage They committed to implement measures to assure that the Operations Control

,

Room will be kept better informed of plant activities whether construction

-

or operation No violations or deviations were identifie . Licensee Action on Previously Identified Items (Closed) Violation 498/499-8502-01, Failure to Follow Procedures -

This item concerned failure to follow procedures regarding the control of temporary material. Procedures CSP-14 and WPP/QCI 12.1 require that material used as a construction aid or used in any other temporary application be identified by painting the item yellow. The NRC inspector observed many instances where nonpermanent material had been used without the yellow paint identification. Some of these temporary installations involved Category 1 material that was to be utilized at a later date in other permanent installations. Site procedures contained no provisions for the retrieval and reuse of Category I material The licensee has made a complete plant walkdown to insure that non-Category I material used in temporary installations or as construction aids is appropriately marked per their respective procedures. Material that is Category I and the " pedigree" is to be maintained during temporary use is being controlled under procedure ASP-5. Several procedural enhancements have been implemented to clarify the requirements for control-of temporary installations. The NRC inspector has reviewed the procedures and performed site tours to verify compliances in the plant. At this l

L

--__-_ - _ _ - _ _

.

.

,

-4-time the licensee is in compliance with their procedural requirement and this violation (498/499-8502-01) is considered close (Closed) Deviation 498/499-8416-01 Component Cooling Water Design This item concerns the failure of the licensee to control system was changed without the required Safety Analysis Report Change Request (SARCR) being prepare The text in FSAR Section 9.2.2 (Amendment 39) reflected the originalReplac chromate inhibitor design of the CCW syste with The design All-Volatile changeTreatment

+.o AVT in the(AVT)

CCWhad been system wasunder review identified on thesince P&ID mid and The" HOLD" was subsequently removed with placed on " HOLD" in July 1933.the At this completion time, the responsibleof the project review and ap on June 5, 1984 (Revision 2, DCN 5).

engineer should have comenced aInFSAR November,texttherevision by initiating a Safety NRC inspectors Analysis Report Change Request (SARCR).

identified P& ids and brought severalthem inconsistencies to the attention of between HL&P (onthe FSAR January text and the is 1, 1985).

Upon notice frcm HL&P, Bechtel begun a review of the FSAR text and the current revision of the P&ID to resolve the inconsistencie Additionally, all Bechtel The appropriate SARCRs have now been issue engineers assigned to the STP have attended a special I hour The lecture NRC on

"FSAR vs. Design - Ccnsistency," course Code 5031, lesson N inspector has reviewed the SARCRs issued for this item, the lesson plan and attendance sheet The licensee's action to correct this specific item and the training provided and complet to the engineer responsible for processing SARCRs as close (Closed) Potentially Reportable 10CFR 50.55(e) -IRC-208 Superheated Steam Condensation Outside Containment Following a MSLB This item concerned a generic notification by Westinghouse that the analysis for a Main Line Steam Break (MLSB) may not have considered the effect containmen of superheated steam on systems and components outs the only suspect location for deleterious effects at STP would be the Isolatinn Valve Cubicles (IVC). At STP, the IVCs are four separate i cubicles (one for each steam line) separated by concrete structural wall No credit is taken for equipment in a cubicle where a rupture oc the event analysi safety item and, therefore, it is not reportable under 10CFR 50.55(e).

The NRC inspector reviewea the various data packages provided Based onfor the analysis, reviewed associated prints and toured the IVC are considered closed.

- - - - _

_ _ _ _ _ _ - _ __ _ _

. >. . ,

~

+ .

l

-5- Plant Maintenance

, The NRC inspector, while observing plant maintenances on turned over equipment,snoted that there was no grease in the motor bearings for Ur.it

-

1, Service Air (SA) compressor Nos.11 and 12. In discussion with

" craftsmen wo_rking on the units it was determined that the motor bearings were dry when disassembled. The bearings for the two Instrument Air (IA)

compressors were also dry. All four compressors are alike and from the same supplier; they differ only in 4pplication. The vendor manual for all the . units indicated they were shipped dry ~and need not be lubricated till just prior to placing in service. However, the two SA units had completed

.

Maintenance Action Cards (MAC) requiring and indicating they had been greased every 6 months. No such MAC cards were found for IA units. The same conditions existed for the Unit 2 IA and SA compressors. Both the SA i'

and IA units at STP are nonsafety-related; however, the NRC inspector is concerned because the MAC car'd system of maintenance is used for both safety and nonsafety equipment. It is not _ clear why the SA compressor

' required grease by the MAC card system and the IA compressor did not. Nor '

is the significance of signed MAC cards for greasing of the SA compressor N when they were found to be grease free on disassembly. Due to the potential impact on safety systems, this is considered an Unresolved Item 498/499-8508-0 No violations or deviations were identifie c' Inplace Protection of Equipment I

During previous inspections the NRC inspectors identified several concerns

_' with~ regard to in-place protection of equipment. A concerted effort to upgrade and improve the protection of inplace equipment has been observed by the NRC inspector. In Unit 1, a large amount of permanent plant

,

equipment.is now located at site-installed locations and with the a . construction effort being at a high level damage or deterioration could easily occur. The licensee has made steady improvement in this area. The NRC inspector has observed fire retardant plastic wrapping, blanking of pipe and equipment opening, wood framed boxing, " angle hair" filter mediums, trace heating and other methods of protection being applied where

'

protection may be required. This effort is an improvement over past

. existing condition No; violations or deviations were identifie . s

4 Onerator Training and Simulator

.The NRC inspector has attended selected operator training classes. This f- included attending portions of lectures on various cold licensing subjects such as IE electrical distribution, steam generator, feed system, et The training was conducted in an organized, professional manner. Class

.attentidn and' participation was good. The trainees were observed in the

' plant on several occasions reinforcing their classroom instruction by

'

tracing out systems and locating equipment. Discussions with students in l

-

-- ,

o

P'--

. . , ,

{'

, 3;

,

,

-6-

! the plant' indicated a basic understanding of the systems and a satisfaction with,the level and quality of instructions provide Work on the installation of the plant' simulator at the training facility was observed by the NRC inspector. Assembly is on schedule and very few unexpected problems are being encountered. The availability of the

' simulator for training should be January 1986, as require No' violations or deviations were identifie ' Startup Activities The NRC-inspector.has been reviewing revisions to the startup manual, prerequisite and generic test procedures. . The revisions have been at the fine tuning level.with no major revision of startup policy., The NRC inspector had not yet received any approved safety,startup procedures because the licensee is behind the published startup schedule. The

' licensee has committed to make available to the NRC the approved startup

. (pre operational) procedures 60 days prior.to the test date. Turnover t startup of completed safety systems has impacted the ability to perform

'

,

preoperational testing so the delay in procedure preparation has had little impact to dat '

The NRC inspector observed the prerequisite testing and energization of the standby transformers which makes plant power available for other system testing. This effort demonstrated a good working relationshi between the startup, operations and maintenance groups and a good-

, coordinated effort at problem resolutio :No violations or deviations were identifie : Exit Interview An' exit interview was conducted on June 28, 1985, with those personnel denoted in paragraph 1-of this report. During the exit interview, the NRC

' inspectors summarized the scope and findings of this inspection.

,

h I '. 9