ML20125C816
| ML20125C816 | |
| Person / Time | |
|---|---|
| Site: | Humboldt Bay |
| Issue date: | 02/29/1984 |
| From: | Sherman C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Wenslawski F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| Shared Package | |
| ML20125C784 | List: |
| References | |
| FOIA-85-007 NUDOCS 8506120167 | |
| Download: ML20125C816 (8) | |
Text
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o FEB 2 9 ng4 MEMORANDUM FOR:
F. A. Wenslawski, Chief Radiological Safety Branch FROM:
C. I. Sherman Radiation Specialist
SUBJECT:
DOCKET NO. 50-133, HUMBOLDT BAY INSPECTION PROGRAM Humboldt Bay Power Plant (HBPP) has recently completed moving all fuel from the reactor to the spent fuel pool.
Based upon the permanent shutdown status of the facility, the defueled node and transfer of all inspection responsibility to DRSSP, a unique inspection program should be developed for the facility. The purpose of this memo is to propose an interim inspection program until HBPP is converted to a possession only license with reduced requirements.
The licensee's plan over the next several years will be to remove as much radioactivity as feasable from the plant, without complete decommissioning of the facility. This plan will require processing liquid waste and solid waste, removal of hot spots and shipment of radioactive material offsite.
]
Until a decommissioning plan is developed, approved by NRC and implemented by the licensee, technical specification requirements for an operating plant remain in effect.
Inspection activities in this interim period should focus j
only on those technical specification requirements considered important to safety and consistent with the defueled reactor mode.
Inspection activities will also focus on applicable parts of 10 CFR dealing with radiation protection, transportation of radioactive materials and classification of waste.
The inspection program will continue to be based on the MC2515 program, however, consistent with the reduced inspection effort identified in the operating plan, only selected modules of the minimum and basic programs will be inspected. Of these modules, only these systems that remain important to safety will be considered in completion of the modules. Note that these nodules are intended for inspector guidance only and should not be constructed as a required inspection program.
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8506120167 850214 0-PEHR FOIA SHAPLEN05-OO7 PDR
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a FEB 2 0 mg4 F. A. Wenslawski 2
I recommend that time be allotted to the various functional areas as follows:
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Module Program 70%
Radiation Protection 45%
Operations and Training 10%
Surveillance 10%
Miscellaneous
_S%
l 70%
Reactive
- 10%
Independent 20%
- Based on facility status, reactive inspection effort can be reduced.
The radiation protection inspection program will stress liquid waste processing, exposure control and ALARA, transportation activities and Part 61 requirements.
Surveillance and operations inspection will focus on technical specification requirements for fuel handling, ventillation systems, radiation monitoring and other spent fuel pool systems.
At such time as a decommissioning plan coupled with a possession only license and revised technical specifications are approved, the inspection program will be revised to reflect the new requirements in order to assure adherence to the decommissioning plan.
In accordance with IE HC0800 (Feedback) contact will be maintained with the NRR PM in order to provide input to technical specification end license changes.
The inspection program provided as enclosure A consist of three portions, operations and surveillance, radiation protection and followup.
It is expected that only the first part will change as the license requirements change.
4/
C. I. Sherman Radiation Specialist RV/jk
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SHERMAN-2/2S/84
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Enclosure A INSPECTION INSPECTION PROCEDURE INSPECTION PROCEDURE TITLE FREQUENCY NO.
Functional Area Inspector Meetings 30703 Management Meeting--Entrance and Exit Q
Plant Operations 41700
. Training A
41701 Requalification Training A
71710 ESF System Walkdown S
Plant Operations 71707 Operational Safety Verification Q
71708-Inspection During Long Term Shutdown Q
Plant Operations 42700 Procedures A
86700 Spent Fuel Pool Activities A
Surveillance 61719 Containment Leak Rate Test
- A 61725 Surveillance Testing and Calibration Program TA 61726 Monthly Surveillance Observation Q
61700 Surveillance Procedures and Records A
61701
-Surveillance--Refueling S
Fire Protection / Housekeeping 64/04 Fire Prevention / Protection Program Implementation BA t
- Applied to refueling building i
1
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INSPECTION INSPECTION PROCEDURE INSPECTION PROCEDURE TITLE FREQUENCY NO.
Functional Area Radiation Protection
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'80721 Radioloafpal Environmental Monitoring (Basic)
BA 83722 Radiation Protection, Plant Chemistry, and Radweste: Organization and Management Controls (Minimum and Basic)
BA 83723 Radiation grotection, Plant Chemistry, Radwaste, and Transportation: Training-Qualifications (Minimum and Basic)
BA 83724 External Occupational Exposure Control and Personal Dosimetry (Minimum and Basic)
A 83725 Internal Exposure Control and Assessment (Minimum and Basic)
A 83726 Control of Radioactive Materials and Contamination, Surveys, and Monitoring (Minimum and Basic)
A 83727 Facilities and Equipment (Basic)
BA 83728 Maintaining occupational Exposures ALARA (Minimum and Basic)
A 83729 Occupational Exposure During Extended Outages (Basic)
A 84722 Solid Wastes (Minimum and Basic)
A 84723 Liquids and Liquid Wastes (Minimum and Basic)
.A 86721 Transportation (Basic)
A xxxxx 10 CFR 61 Requirements A
Inspector Followup 90712 In-Office Review of Event Reports W
92700 Onsite Followup of Written Reports of Nonroutine Events W
92702 Followup Items of Noncompliance W
92703 IE Bulletin /Immediate Action Letter Followup W
93702 Onsite Followup of Events at Operating Reactors W
l
s D.
4 i.
WB29 y MEMORANDUM FOR:
F. A. Wenslawski, Chief
[
Radiological Safety Branch FROM:
C. I. Sherman Radiation Specialist SDMSCT:
DOCKET NO. 50-133. EUMBOLDT BAY INSPECTION PROGRAM 11umboldt Bay Power Plant (REPP) has recently completed moving all fuel from the reactor to the spent fuel pool. Based upon the permanent shutdown status of the facility, the defueled mode and transfer of all inspection tesponsibility to DRSSP, a unique inspection program should be developed for the facility. The purpose of this memo is to propose an interim inspection program until HBPP is converted to a possession only license with reduced reginit tments.
The 14.censee's plan over the next several years will be to remove as much radiesetivity as feasable from the plant, without complete decommissioning of the f cility. This plan will require processing liquid waste and solid waste, remoe 1 of hot spots and shipment of radioactive material offsite.
Until a decommissioning plan is developed, approved by NRC and implemented by the iteensee, technical specification requirements for an operating plant remain in effect.
Inspection activities in this interim period should focus only cc those technical specification requirements considered important to safe.ty and consistent with the defueled reactor mode. Inspection activities will also focus on applicable parts of 10 CFR dealing with radiation protection, transportation of radioactive materials and classification of waute.
The inspection program will continue to be based on the MC2515 program, however, consistent with the reduced inspection effort identified in the operating plan, only selected modules of the minimum and basic programs will be inspected. Of these modules, only these systems that remain important to safety will be considered in completion of the modules. Note that these modules are intended for inspector guidance only and should not be constructed as a required inspection program.
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yt sg
FEB 2 9 gg4
~
F. A. Wenslavski 2
I recommend that time be allotted to the various functional areas as follows:
Module Program 70%
Radiation Protection 45%
Operations and Training 10%
Surveillance 10%
~
Miscellaneous J%
70%
Reactive
- 10%
Independent 20%
- Based on facility status, reactive inspection effort can be reduced.
The radiation protection inspection program will stress liquid waste processing, exposure control and ALARA, transportation activities and Part 61 requirements. Surveillance and operations inspection will focus on technical specification requirements for fuel handling, ventilation systems, radiation monitoring and other spent fuel pool systems.
At such time as a decommissioning plan coupled with a possession only license and revised technical specifications are approved, the inspection program will be revised to reflect the new requirements in order te assure adherence to the decommisaioning plan.
In accordance with IE MC0800 (Feedback) contact will be maintained with the NRR PM in order to provide input to technical specification and license changes.
The~ inspection program provided as enclosure A consists of three portions, operations and surveillance, radiation protection and followup.
It is expected that only the first part will change as the license requirements change.
5/
C. I. Sherman Radiation Specialist 4
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3 Enclosure A INSPECTION.
INSPECTION PROCEDURE INSPECTION PROCEDURE TITLE FREQUENCY NO.
Functional Area Inspector Meetings 30703
. Management Meeting--Entrance and Exit Q
Plant Operations 41700 Training A
41701 Requalification Training A
71710 ESF System Walkdown S
Plant Operations 71707 Operational Safety Verification Q
71708 Inspection During Long Term Shutdown Q
(
Plant Operations 42700 Procedures A
86700 Spent Fuel Pool Activities A
Surveillance 61719 Containment Leak Rate Test
- A 61725 Surveillance Testing and Calibration Program TA 61726 Monthly Surveillance Observation Q
61700 Surveillance Procedures and Records A
61701 Surveillance--Refueling S
Fire Protection / Housekeeping 64/04 Fire Prevention / Protection Program Implementation BA t
[
- Applied to refueling building
(
i e
i INSPECTION INSPECTION PROCEDURE INSPECTION PROCEDURE TITLE FREQUENCY NO.
Functional Area Radiation Protection 80721 Radiological Environmental Monitoring (Basic)
BA 83722 Radiation Protection Plant Chamistry, and Radweste: Organization and Management Controls (Minimum and Basic)
BA 83723 Radiation Protection, Plant Chemistry, Radweste, and Transportation: Training Qualifications (Minimum and Basic)
BA 3
83724 External Occupational Exposure Control and Personal Dosimetry (Minimum and Basic)
A 83725 Internal Exposure Control and Assessment (Minimum and Basic)
A J
t 83726 Control of Radioactive Materials and Contamination Surveys, and Monitoring (Minimum and Basic)
A i
83727 Facilities and Equipment (Basic)
BA 83728 Maintaining occupational Exposures ALARA (Minimum and Basic)
A 83729 Occupational Exposure During Extended Outages (Basic)
A 84722 Solid Wastes (Minimum and Basic)
A 84723 Liquids and Liquid Wastes (Minimum and Basic)
A 86721 Transportation (Basic)
A 9"ECb xxxxx 10 CFR 61 Requirements A
Inspector Followup 90712 In-Office Review of Event Reports W
92700 Onsite Followup of Written Reports of Nonroutine Events W
~
92702 Followup Items of Noncompliance W
92703 IE Bulletin /Immediate Action Letter Followup W
93702 Onsite Followup of Events at Operating Reactor's W
. -.