IR 05000498/1987002
| ML20207S323 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 03/11/1987 |
| From: | Chaney H, Murray B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20207S316 | List: |
| References | |
| 50-498-87-02, 50-498-87-2, 50-499-87-02, 50-499-87-2, IEB-78-08, IEB-78-8, NUDOCS 8703190274 | |
| Download: ML20207S323 (10) | |
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APPENDIX U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report:
50-498/87-02 Construction Permits:
CPPR-128 50-499/87-02 CPPR-129 Dockets:
50-498 Expiration Date: December 31, 1987 50-499 Licensee:
Houston Lighting & Power Company (HL&P)
P. O. Box 1700 Houston, Texas 77001 Facility Name:
South Texas Project Electric Generating Station (STP)
Units 1 and 2 Inspection At:
STP Site, Matagorda County, Bay City, Texas Inspection Conducted:
February 17-20, 1987 3/h Ob Inspector:
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H. D. Chaney, Radiation Speciadist, Facilities Date Radiological Protection Section
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Approved: [ B. M6rray, Chief, Facilities Radiological Date
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Protection Section Inspection Summary Inspection Conducted February 17-20, 1987 (Report 50-498/87-02; 50-499/87-02)
Areas Inspected:
Routine, announced preoperational inspection of the licensee's radiation protection (RP) program, including:
management controls and organization; training and qualification; external radiation exposure control (including spent fuel transfer tube access control); internal radiation exposure control; respiratory protection; radiological posting; radiological surveys; ALARA and radiological work control pro 0 ram; radiation protection instrumentation and calibration; radiation protection facilities; radiation protection equipment and expendable supplies; radiation protection program audits and reviews; and the post-accident sampling system.
Results: Within the areas inspected, no violations or deviations were identified.
Two open items were closed during this inspection.
8703190274 870317 PDR ADOCK 05000498 O
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DETAILS 1.
Persons Contacted HL&P
- W. H. Kinsey, Plant Manager
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- M. A. McBurnett, Supervising Engineer Site Licensing
- G. L. Jarvela, Health & Safety Services (H&SS) Division Manager R. C. Craft, Radiological-Protection Supervisor (RPS)
W. C. Parish, Radiological Support Supervisor
- H. E. Dudley, Nuclear Training Department. (NTD) Supervisor S. Head, Engineer, Project Compliance Group
- E. L. Brown, Project Compliance Engineer W. G. Isereau, QA Audit / Surveillance Supervisor D. F. Bednarczyk, Operations QA Supervisor B. N. Woolweber, Engineer, Operations Technical Support
- J. C. Dierickx, Chemical-Support Supervisor P. Newcomb, Consulting Engineer Others
- D. R. Carpenter, NRC Senior Resident Inspector N. P. Kadambi, NRC Project Manager for STP
- R. E. Hall, Deputy Director, Division of Reactor Safety and
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Projects, NRC Region IV
- K. H. Oh, Senior Research Scientist, Republic of Korea
- Denotes those present during the exit interview.
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2.
Follow-up on Previous Inspection Findings i-l (0 pen) Open Item 498/8629-01: Organization and Management Controls - This l
item involved the licensee's need to resolve the following NRC concerns:
i a.
Development of a program for issuance of reports and notifications t'o
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the NRC.
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b.
Revision of procedures to eliminate erroneous references, and provide
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for supervisory review of survey and technical. documents.
c.
Issuance of a policy statement from s6n.ior HL&P management concerning
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the RP program.
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d.
Address the responsibilities of the STP staff in Procedure OPGP03-ZR-0001.
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The licensee had adequately resolved concerns (b) and (d).
This item will l
remain open pending the licensee's development and NRC review of j
procedures IP 1.4Q and 1.15Q for concern (a), and issuance of a management
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policy for the Radiation Protection (RP) Program for concern (c).
The licensee stated that actions to resolve the remaining NRC concerns would be completed by April 1, 1987.
(Closed) Open Item 498/8629-02:
Organization and Staff Qualifications -
This item concerned the licensee's RP staff's apparent lack of commercial operating reactor experience.
The licensee's response to this item resolved the NRC's concerns in this area.
This item is considered closed.
(0 pen) Open Item 498/8629-03: General Employee Training - This' item concerned the NRC's review of General Employee Training - 1 (GET-1) to determine compliance with the requirements of 10 CFR Part 19.12.
This item was not reviewed during this inspection and will remain open pending review by the NRC during future inspections.
(0 pen) Open Item 498/8629-04:
Radiological Worker Training - This item concerned the licensee's training program for radiological workers, including respiratory protection equipment (RPE) training (GET 2 & 3).
The licensee needed to resolve the following NRC concerns:
a.
Include RP staff's stop work authority in GET 2 and 3.
b.
Provide RPE (GET-3) instructors with appropriate technical training.
c.
Evaluate the completeness of GET-3 training in regards to all RPE available at STP.
d.
Provide policy statements concerning the RP program to all personnel that attend GET.
The licensee had adequately resolved concerns (a) and (c). The licensee stated that concern (b) will be completed by May 1, 1987, when selected Nuclear Training Department instructors will have completed vendor provided RPE technical training.
The concern regarding HL&P RP/RPE/ALARA policies to GET attendees will be completed by April 1, 1987, along with issuance of the HL&P policies referenced in Open Items 498/8629-01 and 08.
(0 pen) Open Item 498/8629-05:
Radiation Protection Staff Training - This item concerned the licensee's presentation and documentation of training identified in the Final Safety Analysis Report (FSAR).
The licensee
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needed to resolve the following NRC concerns:
a.
Properly document training waivers for H&SS Department personnel.
b.
Verify that all training addressed in the FSAR has been completed for H&SS Department personnel.
The licensee was still working on this item at the time of the inspection.
The licensee stated that this item would be completed by April 1, 1987.
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i (0 pen) Open Item 498/8629-06:
External Radiation Exposure Control - This item concerned the licensee's dosimetry program for external exposure and involved the licensee's need to resolve the following NRC concerns:
a.
Evaluation of the thermoluminescent dosimeter (TLD) algorithm used t'o establish whole body radiation exposure to. satisfy 10 CFR Part 20.401 i
requirements.
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b.
Establish accreditation for the beta and neutron radiation monitoring component of the TLO.
c.
Complete development of implementing procedures for the personnel exposure monitoring program.
d.
Procure suitable pocket dosimeters to satisfy equipment commitments s9, in the STP Emergency Plan.
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e.
Establish corrective actions for controlling access to areas adjacent to the Unit 1 spent fuel transfer tube.
f.
Evaluate the temperature limitations of personnel TLDs.
The licensee had adequately' resolved the NRC's concerns regarding (a),
(b), (c), and (d). The lichnsee had n'ot completed evaluation of the temperature limitations of their TLDs for concern (f).
Item (f) is
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scheduled to be completed by April 1, 1987.
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The NRC inspector reviewed access controls associated with the fuel transfer tube to determine agreement with Inspection and Enforcen'ent (IE)
Item _e:
Based on an inspection of the accessible areas is surrounding the unshielded fuel transfer tube between Unit 1 containment
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and the spent fuel pool, the NRC inspector determined that the licensee's proposed controls which consist of locking the two doors that provide (P access to equipment rooms adjacent to the exposed fuel transfer tube, is
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unacceptable.
The licensee states that the present arrangement to control
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P a access to the transfer tube would be reviewed along with methods to improve access controls.
The NRC inspector noted that the present controls agree hith commitments in the FSAR; however, these controls do not appear to be adequate.
The NRC inspector stated that this matter would be coordinated with the NRC STP project manager.
Corrective actions for the improvement in access control for the spent fuel tube area need not be completed until prior to the first movement of irradiated fuel assemblies. The licensee was advised that this concern will also apply to Unit-2.
This concern will remain open pending further licensee actions to ensure that the requirements of IE Bulletin 78-08 are satisfied.
b (0 pen) Open Item 498/8629-07:
Internal Exposure Control - This item
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concerned the licensee's program for assessing internal exposures to
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radioactive material (RAM) and the need for the licensee to resolve the following NRC concerns:
a.
Development of an in-vitro bioassay sampling procedure.
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b.
Develop methodologies for the determination of maximum permissible concentration hours of uptake using bioassay results.
The licensee had adequately resolved concern (a) by issuance of procedure OPGP03-ZR0027.
This item will remain open pending licensee actions to resolve concern (b).
The licensee stated that this matter is scheduled to be completed by April 1, 1987.
(0 pen) Open Item 498/8629-08:
Respiratory Protection - This item concerned the licensee respiratory protection program and the licensee's need to resolve the following NRC concerns:
a.
Issuance of a respiratory protection policy that agrees with NRC Regulatory Guide 8.15 guidance.
b.
Designating, in writing, the site contact for respiratory protection program inquiries.
c.
Evaluate the minimum inventory requirements for respiratory protection equipment (RPE) to support outage and emergency preparedness activities.
The licensee had adequately resolved concern (c) by procurement of additional RPE.
Concerns (a) and (b) are scheduled to be completed by April 1, 1987.
(0 pen) Open Item 498/8629-09:
Radiological Posting - This item concerned the licensee's radiological posting program and the need to develop specific procedures for the periodic review of posting and verification of high radiation area access controls.
The licensee scheduled completion of actions for this item for April 1,1987.
(0 pen) Open Item 498/8629-10:
Radiological Surveys - This item involved the licensee's radiological monitoring and survey program, and the need for the licensee to resolve the following NRC concerns:
a.
Development of an in plant airborne sampling program for iodine radioactivity during reactor accidents (NUREG-0737).
b.
Development of a reactor shield survey program that satisfies the recommendations of ANSI /ANS 6.3.1-1980.
c.
Establish a proper survey program for release limits concerning potentially contaminated materials.
d.
Include in routine operating procedures, that are cross referenced in emergency preparedness procedures (for use during reactor accidents),
specific emergency response instructions.
The licensee had developed an airborne iodine sampling and measuring program for in plant /onsite activities during a reactor accident that satisfactorily resolves concern (a).
The NRC inspector verified that routine operating procedures and/or emergency preparedness implementing
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procedures, when cross referenced, provided suitable information to users during emergencies to resolve concern (d).
The licensee had developed a reactor shield survey program and submitted it to the Plant Operations Review Committee for approval for action on concern (b).
The NRC inspector determined that the licensee needed to verify that suitable signature verification was included in either the startup test program or the shield survey procedure to ensure that each step of the shield survey (power ascension plateaus) was completed and reviewed, and that the full power radiation levels were in agreement with the FSAR radiation zones.
The licensee had scheduled concerns (b) and (c) for completion by April 1, 1987.
(Closed) Open Item 498/8629-11:
ALARA and Radiological Work Controls -
The items involved the licensee's ALARA program implementing procedures and the Radiation Work Permit (RWP) program.
The NRC concerns were as follows:
a.
Complete development of an RWP program.
b.
Completion of ALARA program implementing procedures.
The NRC inspector verified that issuance of RWP Procedure (0PG03-ZR-0002)
and ALARA procedures (0PRP03-ZT-002 and OPGP03-ZR-0030) resolves concerns (a) and (b).
This item is considered closed.
(0 pen) Open Item 498/8629-12:
RP Instrument and Equipment Use/ Calibration
- This item involved the licensee's need to procure the instrumentation identified in the FSAR and develop use and calibration procedures:
a.
Procurement of remaining RP instrumentation.
b.
Completion of use and calibration procedures for RP instrumentation.
The licensee had adequately resolved concern (a) by procuring the identified RP monitoring instrumentation.
The NRC inspector noted that not all use and calibration procedures for RP instruments had been issued.
Concern (b) remains open pending licensee issuance of the remaining procedures for use and calibration of RP instruments.
(0 pen) Open Item 498/8629-13:
Radiological Control Facilities - This item involved the licensee's facilities for in plant offices, decontamination areas, training facilities, etc., and the need for the licensee to complete construction and acceptance of the facilities.
The NRC inspector determined that the licensee had accepted all facilities except for:
Laundry facility Radioactive material / equipment decontamination shop This item will remain open pending licensee completion of the above noted facilities.
(0 pen) Open Item 498/8629-14:
RP Equipment and Expendable Supplies - This item involved the licensee's inventories of expendable RP supplies, RP
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support equipment (portable ventilation system, temporary shielding, etc.), and the need to complete the following:
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Complete procurement of RP equipment and expendable supplies for Unit 1.
b.
Stocking and placement of emergency kits to support the STP Emergency Plan.
The licensee had procured sufficient expendable supplies and support equipmer.t to adequately resolve concern (a).
Concern (b) will remain open pending licensee completion of stocking and placement of emergency kits to support the Emergency Plan.
(0 pen) Open Item 498/8629-15: Audits and Reviews - This item involved the licensee's audit and review of the RP program by the Quality Assurance Department, and the need to resolve the following NRC concerns:
a.
Development of audit plans for the STP RP program.
b.
Defining the specific audit and review functions of the Nuclear Safety Review Board and the Independent Safety Engineering Group in regard to the review / audit of RP program activities.
c.
Conduct a comprehensive audit of the RP program.
The licensee had developed adequate audit plans and audit schedules for the STP RP program to resolve concern (a).
The NRC inspector did not complete the review of concern (b) during this inspection.
This will be reviewed during a future inspection.
Concern (c) is scheduled to be resolved by the licensee during March 1987.
(0 pen) Open Item 498/8629-16:
Post-Accident Sampling System (PASS) - This item involved the licensee's PASS and the need to resolve the following NRC concerns:
a.
Developing corrective action for the elimination or containment of mechanical joints on the sample lines feeding the liquid grab sample panel, b.
Evaluate relocation of the area radiation monitor (ARM) servicing the PASS cubicles including the locations of any remote readouts.
The licensee had developed a proposal for enclosing the mechanical joints within a metal cabinet equipped with a drain system.
The licensee stated that the cabinet would be installed by April 1, 1987.
The licensee also committed to procuring and installing two additional portable ARMS in the PASS cubicles.
This item is considered open pending installation of the cabinet and ARMS.
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Program Areas Inspected The following program areas were inspected.
Unless otherwise noted, the inspection was completed and revealed no violations, deviations,
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unresolved items, or open items.
Notations after a specific inspection item are used to identify the following:
I = item not inspected or only partially inspected; V = violation; D = deviation; U = unresolved item; and 0 = open item.
Inspection Procedure Inspection Requirements 83522 Radiation Protection, Plant Chemistry, Radwaste, and Environmental:
Organization and Management Controls 02.01 Organization, Responsibilities, and Authorities 02.02 Staffing 02.03 Identification and Correction of Weaknesses 02.04 Audits and Appraisals-0 02.05 Communication to Employees-0 02.06 Documentation and Implementation 83523 Radiation Protection, Plant Chemistry, Radwaste Transportation and Environmental:
Training and Qualifications 02.01 Training and Qualifications Program-0 02.02 Education and Experience 02.03 Adequacy 83524 External Occupational Exposure Control and Personal Dosimetry 02.01 Physical Controls-0 02.02 Administrative Controls 02.03 Personal Dosimetry-0 83525 Internal Exposure Control and Assessment 02.01 Administrative Controls-0
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02.02 Engineering Controls 02.03 Respiratory Protection Equipment 02.04 Air Sampling for Assessing Individual Exposure 02.05 Bioassays 83526 Control of Radioactive Materials and Contamination, Surveys, and Monitoring 02.01 Area Radiation and Airborne Radioactivity Monitors 02.02 Portable Survey, Sampling, and Contamination Monitoring Instruments-0 02.03 Protective Clothing and Equipment 02.04 Radioactive Material and Contamination Control 02.05 In plant Surveys and Monitoring-0 83527 Facilities and Equipment 02.01 Facilities-0 02.02 Equipment 83528 Maintaining Occupational Exposures ALARA 02.01 Management Policy 02.02 Assignment of Responsibilities and Authorities 02.03 Procedures and Standards 02.04 Indoctrination and Instruction 02.05 Reviews of Design and Equipment Selection TI 2514/01 Task II.B.3 Post-Accident Sampling 92703 IE Bulletin, Confirmatory Letter, and Generic Letter Follow-up
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02.01 Bulletin Review-0 02.02 Confirmatory Action Letter Review-I 4.
Exit Interview The NRC inspector met with NRC personne1~and licensee representatives identified in paragraph 1 at the conclusion of the inspection on
February 20, 1987.
The NRC inspector stated that open items addressed in j
this report will be used to track areas requiring either further
inspection or completion of licensee action and that these items need to be resolved before issuance of an operating license.
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