View source for L-77-252, 08/16/1977 Letter Finding No Proprietary Information in Inspection Reports 05000250/1977014 and 05000251/1977014

{{Adams
| number = ML18227A531
| issue date = 08/15/1977
| title = 08/16/1977 Letter Finding No Proprietary Information in Inspection Reports 05000250/1977014 and 05000251/1977014
| author name = Uhrig R
| author affiliation = Florida Power &amp; Light Co
| addressee name = Moseley N
| addressee affiliation = NRC/IE, NRC/RGN-II
| docket = 05000250, 05000251
| license number = DPR-031, DPR-041
| contact person = 
| case reference number = IR 1977014, L-77-252
| document type = Inspection Report, Inspection Report Correspondence, Letter type:L
| page count = 11
}}

=Text=
{{#Wiki_filter:P. O. BOX 013100, MIAMI, FL 33101
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FLORIOA POWER & LIGHT COMPANY August 15, 1977 L-77-252 Mr. Norman C. Moseley,  Director, Region Office of Inspection and Enforcement II U. S. Nuclear Regulatory Commission 230 Peachtree Street, N. W., Suite 1217 Atlanta, Georgia 30303

==Dear Mr. Moseley:==

Re:  RII:FJ 50-250/77-14 50-251/77-14 Florida Power & Light Company has reviewed the subject inspection eport. There is no proprietary information in the report.
Very truly yours, obert E. Uhrig Vice President REU/MAS/cpc cc:  Robert Lowenstein, Esquire

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0                            REGION II 230 PEACHTREE STREET, N.W. SUITE 1217 ATLANTA,GEORGIA 30303 4**~4                              JUL 2 5 1977 In Reply Refer To:
RII:FJ 50-250/77-14 50-251/77-14 Florida Power and Light Company Attn: Dr. R. E. Uhrig, Vice President of Nuclear and General Engineering P. 0. Box 013100 9250 West     Flagler Street Miami, Florida        33101 Gentlemen:
This refers to the inspection conducted by Mr. F. Jape of this office on July 11-14, 1977, of activities authorized by NRC Operating License Nos. DPR-31 and DPR-41 for the Turkey Point Unit 3 and 4 facilities, and to the discussion of our findings held with Mr. H. E. Yaeger at the conclusion of the inspection.
Areas examined during the inspection and our findings are discussed in the attached inspection report. Within these areas, the inspection consisted of selective examinations of procedures and representative records, interviews with personnel, and observations, by the inspector.
Within the scope of this inspection, no items of noncompliance were disclosed.
We   have examined actions you have taken with regard             to previously identified inspection findings.          These are discussed      in the attached inspection report.
In accordance with Section 2.790 of the NRC's "Rules of Practice,"
Part 2, Title 10, Code of Federal Regulations, a copy of this letter and the attached inspection report will be placed in the NRC's Public Document Room. If this report contains any information that you believe it to'e proprietary, is necessary that you submit a written application to this office requesting that such information be withheld from public disclosure. If no proprietary information is identified, a written statement to that effect should be submitted. If an application is

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Florida  Power and Light Company    submitted,  it must fully identify the bases for which information is claimed to be proprietary. The application should be prepared so that information sought to be withheld is incorporated in a separate paper and referenced in the application since the application will be placed in the Public Document Room. Your application, or written statement, should be submitted to us within 20 days.      If we are not contacted as specified, the attached report and this letter may then be placed in the Public Document Room.
Should you have any questions concerning this     letter, we will be  glad to discuss them with you.
Very    truly yours,
                                          /
F. J. Lo , Chief
                                      ~   ~
Reactor Operations and Nuclear Support Branch

==Attachment:==

RII Inspection Report  Nos.
50-250/77-14 and 50-251/77-14

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      ++*++
Report Nos.:       50-250/77-14 and 50-251/77-14 Docket Nos.:       50-250 and 50-251 License Nos.:       DPR-31 and DPR-41 Licensee:      Florida Power and Light Company P. 0. Box 013100 9250 West Flagler Street Miami, Florida 33101 Facility     Name:   Turkey Point Units        3 and 4 Inspection at:       Turkey Point Site, Homestead,            Florida Inspection conducted:         July 11-14,      1977 Inspector:      F. Jape Reviewed by:       E C.                                                  7h /77 R. C. L'ewis,    Chief                                      Date Reactor Projects Section No.           2 Ins ection     Summa Ins ection on Jul 11-14 1977                Re ort Nos. 50-250/77-14 and 50-251/77-14 Areas Ins ected: Routine, unannounced inspection of plant operations at Units     3 and 4, and of investigative activities involving locating the eleven missing steam generator tube plugs at Unit 4. The inspection involved 28 inspector-hours at the site by one NRC inspector.
Results: Of the three areas inspected, no items of noncompliance were identified.

RII Rpt. Nos. 50-250/77-14 and   50-251/77-14 DETAILS                 Prepared by:                                     7<J y7 F.'ape, Reactor Inspector               Date Reactor Projects Section No. 2 Reactor Operations and Nuclear Support Branch Dates  of Inspection:    July 11-14,  1977 Reviewed by:   Q.C,                               71~>/77 R. C. Lewis, Chief                      Date Reactor Projects Section No. 2 Reactor Operations and Nuclear Support Branch
: 1. Persons Contacted Florida  Power and  Li ht  Com  an   FP&L J. K. Hays, Plant Superintendent, Nuclear H. E. Yaeger, Plant Manager J. E. Moore, Superintendent, Nuclear Operations G. G. Jones, Plant Supervisor, Nuclear J. Smith, Control Center Operator D. D. Brady, Plant Supervisor, Nuclear J. Whitehead, Watch Engineer W. C. Miller, Plant Training Coordinator, Nuclear K. Metzger, Watch Engineer Westin house   Electric  Cor oration   (W E. Manning, Engineer J. Headon, Refueling Coordinator
: 2. Licensee Action on Previous Ins ection Findin s Unresolved Item
(   en  77-12/I:2 Missin     Ex  losive Plu from    4B Steam Generator Followup on this unresolved item was continued. Licensee has reported that the number of missing plugs is eleven. Investigative activities to locate the missing plugs was unsuccessful and refueling was initiated on July 13, 1977.      Item remains open pending receipt and review of licensee event report.       (paragraph 5)

RII  Rp   t. Nos. 50-250/77-14 and 50-251/77-14
: 3.      Unresolved Items None
: 4.      Exit Interview An   exit management interview was held with H. Yaeger and J. Hays on July 14, 1977.      The inspector summarized the scope and findings of the inspection.      The licensee representative made the following remarks    in response to certain items discussed by the inspector:
Acknowledged that eleven plugs from 4B steam generator are unaccounted for. (paragraph 5)
Stated that   a  metal impact monitoring system will be installed on the Unit   4  reactor vessel and functionally tested prior to resuming power operation.      (paragraph 5)
: 5.      Steam Generator Tube      Plu  s  Unit 4 The   licensee notified Region II, on June 25, 1977, that ten steam generator tube plugs were missing from the cold leg side of 4B Steam Generator.       In addition, the tube plug reported missing on May 23, 1977, has not been located, for a total of eleven missing plugs   o The search,     using a TV camera suspended thru the lower core plate, did not locate any of the missing plugs in the reactor vessel. A TV camera mounted on a sled was inserted into RCS cold leg piping between the steam generator and the RC pump in an effort to locate the plugs. None were observed. The inspector witnessed this operation and viewed selected portions of the video tapes previously taken. The search efforts appeared to be thorough and professional.
Other investigative efforts included visual observation of the upper internals and radiographic examination of drains and other lines wherein the plugs could have become lodged. No plugs were found.
After completing the search, the licensee concluded that the plugs were not in the primary system and efforts to refuel the reactor were initiated. The licensee intends to summarize their investiga-tive efforts and findings in the forthcoming reportable occurrence report. Discussions with licensee management concerning monitoring plans during reactor operation revealed that a metal impact monitoring system is to be installed and operational prior to resuming power operation.

RII Rpt. Nos. 50-250/77-14 and 50-251/77-14 Followup on    this unresolved item     will be  continued on future inspections.
: 6. Review   of Plant   0  erations The opera'tion of Units 3 and 4 was reviewed to determine confor-mance with Technical Specifications and regulations.           This was done by reviewing operating records,       touring accessible plant areas and discussing selected items with licensee personnel.
: a. Plant  0  eratin    Records The following plant operating       records, required by   TS  6.8.1 and 6.10 were reviewed:
: l. Unit 3 and -4 Nuclear Control Center Operators log for July 1-12, 1977,
: 2. Unit 3 and 4 Nuclear Plant Supervisors log for July 1-12, 1977,
: 3. Unit   3  Auxiliary Operators    Data Sheets  for July  12, 1977,
: 4. Jumper logs     for Units  3 and  4,
: 5. Clearance logs      for Units 3 and 4 for June and July,
: 6. Letters of Instruction for the past month.
Within the areas examined, no items of noncompliance were identified.
: b. Plant Tour A  tour was conducted of the following areas: auxiliary building, cable spreading room, Unit 4 reactor building, turbine area and the control center for Units 3 and 4. The areas were reviewed for housekeeping conditions, piping leaks and vibrations and radiation controls. The tour was conducted in the accompaniment of a watch engineer during the third shift of the day. During the tour various switch and valve positions, control room annunciators, equipment lock out tags and staffing requirements were checked.         The inspector inter-viewed several nuclear control operators concerning their

RII Rpt. Nos. 50-250/77-14 and 50-251/77-14 cognizance of annunciators and system status. In each case, the operators were fully aware of the plant systems and the annunciators requiring attention.
The inspector also witnessed  a portion of the Unit 4 refueling activities. The activities in the reactor building and control center were observed. The refueling activities were directly being supervised by a senior Reactor Operator and the refueling procedure was being followed. Necessary changes to the procedure were made as delineated in TS 6.8.2 and 6.8.3.
Within the areas examined  and toured, no items of noncom-pliance were identified.

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