IR 05000400/1991025
| ML18010A497 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 11/20/1991 |
| From: | Christensen H, Tedrow J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18010A496 | List: |
| References | |
| 50-400-91-25, NUDOCS 9201170131 | |
| Download: ML18010A497 (4) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTASTREET, N.W.
ATLANTA,GEORGIA 30323 Report No.:
50-400/91-25 Licensee:
Carolina Power and Light Company P. 0.
Box 1551 Raleigh, NC 27602 Docket NoeI 50-400 Facility Name:
Harris-1 Inspection Conducted:
October 21 - November 16,. 1991 Lead Inspector:
J.
Tedrow, Senior Resi nt Ins ector Other Inspector(s):
M. Shannon, Resident Inspector Approved by:~ H.
Chr stensen, Section Chief Division of Reactor Projects License No.:
NPF-63 J/z~ y ate signed I] Zu lt Dat Si ned SUMMARY Scope:
This special inspection was conducted by two resident inspectors to review the licensee's program to periodically review and evaluate changes to the environs around the reactor facility.
Results:
No violations or deviations were identified.
The FSAR adequately addressed current safety hazards around the site.
However, the licensee's method for monitoring the environs for potential hazards was considered to be informal, paragraph 2.
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REPORT DETAILS 1.
Persons Contacted Licensee Employees R. Bassett, Senior-Specialist, Emergency Preparedness S. Floyd, Manager, Nuclear Licensing Section R. Goodwin, Project Specialist, Corp.
Emergency Preparedness P. Morris, Manager, Licensing Support Unit
- C. Olexik, Manager, Regulatory Compliance
- R.-Prunty, Manager, Harris Nuclear Plant Licensing
- M. Wallace, Senior'pecialist, Regulatory Compliance Other licensee employees contacted included office, Operations, Engineering, Maintenance, Chemistry/Radiation and Corporate personnel.
Acronyms and initialisms used throughout this report are listed in'he last paragraph.
2.
Review of Licensee Evaluations Regarding Changes to the Environs Around Licensed Reactor Facilities (30702B)
(Closed)
TI 2515/112:
This inspection was performed to verify that the licensee properly evaluated safety issues which had arisen from 'changes made near the reactor, site involving population distribution or the introduction of new industrial, military, or transportation hazards.
The following documents were reviewed by the inspectors during this effort:
Final Safety Analysis Report (FSAR)
NUREG-1038, Safety Evaluation Report Related to the Operation of Shearon Harris Nuclear Power Plant
CFR Parts 50.71 and 100 NRC Generic Letter 81-06, Periodic Updating of Final Safety Analysis Reports Annual Radiological Environmental Operating Reports Through these reviews and discussions with licensee personnel, the inspectors determined that the licensee did not have a concise program to periodically review the local area around the reactor site for new hazards.
However, the licensee considered a compilation of various plant procedures, and practices provide'd a
means to adequately identify,
'evaluate, and report any safety significant changes to the surrounding environmen The licensee's process of initiating FSAR changes was specified in plant procedure AP-603, FSAR Revisions.
This procedure contained a brief statement r'equiring plant personnel responsible
,for applicable FSAR sections to submit proposed changes to correct inaccurate information.
To initiate this process, Nuclear Licensing personnel would notify applicable area managers through interoffice correspondence.
The inspectors reviewed several of these memos and noted that special emphasis was applied to FSAR chapters 2, 3, and 13 in the latest memo.
This special emphasis appeared to be a direct response to the issuance of TI 2515/112.
After initiation, submittals were then forwarded to Nuclear Licensing and compiled into a FSAR revision submittal to the NRC.
No requirements were found in the licensee procedures which required a
periodic review of the environs to specifically identify and evaluate site proximity hazards or to identify changes in the local population density.
Nevertheless, licensee personnel were aware of these types of changes through routine communications/meetings with county emergency planning organizations.
This communication focused primarily on potential evacuation of the nearby population.
Also, the Technical Specifications requires a land use census be performed annually.
This census includes the land located within five miles of the plant, but
" focuses primarily on the radiological environmental monitoring program.
In response to the issuance of this TI, the licensee performed an internal review of the information provided on the environs in the FSAR.
No safety significant inaccurate information was identified.
The licensee's review did identify a change in the designation of the nearby population center from Raleigh, NC, to Cary, NC, and 'also identified errors in the predicted population growth tables provided in the FSAR.
This item was not deemed to be significant based on the NRC safety evaluation report already recognizing this potentiality.
The inspectors reviewed chapters 2,
3 and 13 of the FSAR and toured the immediate vicinity surrounding the si.te to identify potentially new safety hazards.
The FSAR review revealed that changes had been made indicating that the licensee had not ignored these sections.
The tour included a visit to the main dam for Harris Lake and the area presently being considered as a possible low-level radioactive material waste dump.
No unreviewed safety hazards were identified.
In conclusion, the inspectors found that the applicable chapters in the FSAR addressed the current safety hazards around the site.
The licensee's method for monitoring the environs for potential hazards was considered to be informal.
The relatively new licensed status of.the facility contributed to the accuracy of the information provided in the FSAR.
However, the informal process for updating the information may not be sufficient to maintain this accuracy as the plant ages significantl.
Exit Interview (30703)
The inspectors met with licensee representatives (denoted in paragraph 1)
at the conclusion of the inspection on November 15, 1991:
During this meeting, the inspectors summarized the scope and findings of the inspection as they are detailed in this report.
The licensee representatives acknowledged the inspectors'omments and did not identify as proprietary any of the materials provided to or reviewed by the inspectors during this inspection.
4.
Acronyms and Initialisms CFR FSAR-NRC TI Code of Federal Regulations Final Safety Analysis Report--
Nuclear Regulatory Commission Temporary Instruction