IR 05000003/1982001
| ML20055B451 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 06/29/1982 |
| From: | Crocker H, Terc N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20055B449 | List: |
| References | |
| 50-003-82-01, 50-247-82-02, 50-247-82-2, 50-3-82-1, NUDOCS 8207220347 | |
| Download: ML20055B451 (27) | |
Text
,
.
,
U.S. NUCLEAR REGULATORY COMMISSION
REGION I
50-003/82-01 Report No. 50-247/82-02 50-003 Docket No. 50-247 License No. OPR-26 Priority.
Category C
Licensee: Consolidated Edison Company 4 Irving Place New York, New York 10003 Facility Name: Indian Point Unit Nos. 1 and 2 Inspection at: Buchanan, New York
<
Inspection conducted:
February 8-11, 1982 f
NRC Personnel,
/M
/>
k Nemen"M. Terc, DEPO RI, NRC
'
date /siefned Cheryl A. Sakenas, DEPOS, RI, NRC Thomas H. Essig, Battelle, NW Wayne H. Knox, Battelle, NW M.
b Approved by g
,
r-H. E Cr6cker, E+ri'ef Emergency T c}dte sogfied Preparedness Section, DEPOS, RI, NRC
,
Inspection Summary:
Inspection on February 8-11, 1982 (Combined Report No.
50-003/82-01; 50/247/82-02)
Areas Inspected:
Special. announced inspection follow-up of emergency preparedness items from a prior appraisal performed on May 11-20, 1981 (Report Nos. 50-003/81-01; 50-247/81-06). The inspection involved 96 inspector-hours onsite by two regionally based inspectors and two NRC contractors.
,
8207220347 820708 PDR ADDCK 05000003 C
.
..
.__
_
_ _ _ _
_
_
,
.
.
.
DETAILS 1.
Persons Contacted W. Bell, Material Controller K. Burke, Director, Regulatory Affairs M. Byster, Senior Quality Assurance Engineer A. Cheifetz, Acting General Vanager, Planning & Technical Support J. Cullen, Radiation Protection Manager
,
J. Curry, Chief Operating Engineer H. Dohr, Personnel Administrator A. Ferarro, Radiation Protection Training Administrator J. Higgins, Chemistry Manager C. Jackson, Vice President F. Karp, Nuclear Licensing Specialist B. Lindgren, Manager, Nuclear Information G. Leibler, Emergency Planning Director E. McGrath, Senior Vice President, Power Generation D. Rosh, General Manager, Technical Support M. Shatkouski, General Manager, Administrative Services W. Thompson, Consultant, Quality Assurance S. Wisla, General Manager, Environmental Health and Safety In addition to the above, the auditors contacted other members of the licensee staff.
2.
General During the period May 11-23, 1981, the NRC conducted an appraisal of'the state of emergency preparedness for the Indian Point Station Units 1 & 2.
As a result of this appraisal, the NRC identified 56 significant findings which required resolution to achieve an adequate state of emergency prepared-ness.
In addition, the NRC identified 40 improvement items. These findings were documented in a letter to the licensee dated June 12, 1981, and an
office of Inspection and Enforcement Combined Inspection Report Number 50-03/81-01; 50-247/81-06.
In a letter to the NRC, dated September 30, 1981, the licensee committed himself to resolve all significant findings (Appendix A) within 120 days, and all improvement items (Appendix B) within 180 days.
The purpose of this inspection was to review the status of the licensee's corrective actions.
3.
Licensee Action on Previous Inspection Findings 3.1 (Closed) 50-003/81-01-01; 50-247/81-06-01 Formal assignment of a Corporate Emergency Planning Coordinator who is given direct working level responsibility for and authority over all
'
aspects of the development and maintenance of the corporate emergency response capability and provided sufficient time to perform emergency planning duties (Appendix A, item 1).
-
,
, -
.
_. - =.
-
-
,
,
1
.
.
The auditors verified that in a letter dated September 21, 1981, signed by the Senior Vice President, Power Generation, Dr. A. S. Cheifitz was designated as the Corporate Emergency Response Plan Coordinator with responsibility to implement and maintain Section 12 of the Emergency Plan and Administrative Procedures I and 2.
This item is closed.
3.2 (Closed) 50-003/81-01-C2; 50-247/84-06-02 Implementation of administrative provisions to ensure that the site Ef 's assigned responsibilities are supported with sufficient authority to.llow implementation of his duties (Appendix A, item 2).
The auditors confirmed that the revised Position Guide for the EPD assigned him the responsibility to coordinate emergency plan implementa-tion in all sections of Nuclear Power and to report deficiencies to the General Manager, Environmental Health and Safety.
This item is closed.
3.3 (Closed) 50-003/81-01-035; 50-247/81-06-03 Administrative provisions to insure adequate coordination between emergency organizational elements at the site, between the site and corporate headquarters, between the site and the general public, and between the site and the news media (Appendix A, item 3).
The auditors confirmed that the Manager, Nuclear Information, was assigned to serve as: the liaison between the site and Public Infor-mation, emissary to the general public, and plant spokesperson to the news media.
These responsibilities were outlined in his Position-Guide and in procedure CERP-IP-8.
This item is closed.
3.4 (Closed) 50-003/81-01-06; 50-247/81-06-06 Revision of the emergency organization and its description to provide all emergency functions during initial, intermediate and final phases of its augmentation. Such description shall provide a sufficient level of detail to: completely and unambiguously delineate the command hierarchy; clearly specify its structure, reporting chains and inter-relationships at any phase of augmentation; and include supervisory, as well as, non-supervisory elements (Appendix A, item 4).
The auditors verified that the licensee had revised their emergency organization according to the intent of the finding and included this description in Section 5.2 of Emergency Plan and IP-1001.
This item is close.
.
.
.
3.5 (Closed) 50-003/81-01-07; 50-247/81-06-07; Provision of approved lists of personnel in the emergency organization segregated by individual training qualification which reflect each functional area specified within the revised emergency organization.
These lists shall identify the current training status of each indi-vidual. Provisions tu maintain the lists current shall be developed and implemented (Appendix A, item 5).
The auditors verified that the revision of Appendix A to the Emergency Plan, " Site Emergency Roster" included retraining dates for each individual and their qualification for specific emergency response functions.
This item is closed.
3.6 (Closed) 50-003/81-01-08; 50-247/81-01-08 Incorporation of the Corporate Emergency Response Plan (CERP) into the
,
site Emergency Plan by additional reference and further definition and
'
clarification of the command hierarchy, reporting chains and working inter-relationships between the corporate organization and the onsite emergency organization (Appendix A, item 6).
The auditors verified that the revised Emergency Plan incorporated the CERP into Section 9 and that site emergency response functions were found in the corporate emergency response organization (Figure 9.1-1.)
This item is closed.
3.7 (Closed) 50-003/81-01-09; 50-247/81-06-09 Realignment of the emergency plan training program with the functional areas of erergency activity in the emergency organization so that the training categories are consistent with the requirements and structure of the emergency organization (Appendix A, item 7).
The auditors verified the realignment of the training program, (described in Section 8 of the Emergency Plan and Section 14 of the Indian Point Station Training Manual) into functional areas of emergency activities and made in such manner that training categories are consistent with the structure of their emergency organization.
This item is closed.
3.8 (Closed) 50-003/81-01-10; 50-247/81-06-10 Consolidation within the Nuclear Training Section of the responsibility and authority for all phases of the emergency plan training program including control of course development and instructors obtained from sections other than the Nuclear Training Section (Appendix A, item 8).
.
.
.
.
The auditors confirmed that the Indian Point Station Training Manual was revised to specify responsibility for coordination of emergency plan training and for maintaining training records with the Nuclear Training Section.
This item is closed.
3.9 (Closed) 50-003/81-01-11; 50-247/81-06-11 Development of an emergency plan training program for training indi-viduals and groups in all functional areas of emergency activity including as a minimum:
lesson plans; student performance objectives to be met; the means for verifying attendee accomplishments against the student performance objectives; and the means by which completed training will be documented to verify that all required training has been performed (Appendix A, item 9).
The auditors reviewed:
New lesson plans, performance objectives, examinations and attendance verification forms and found them to be satisfactory.
This item is closed.
3.10 (Closed) 50-003/81-01-13; 50-247/81-06-13 Development and implementation of a comprehensive emergency plan training program to ensure that the specific licensee and non-licensee-individuals or groups assigned to the various functional areas of emergency activity receive training and attain a level of proficiency to permit them to perform emergency duties assigned in accordance with the response scheme outlined in the Emergency Plan (Appendix A, item 10).
The auditors confirmed that a training program was augmented to cover all categories of emergency workers, including non-licensee personnel.
This item is closed.
3.11 (0 pen) 50-003/81-01-15; 50-247/81-06-15 Provisions for a TSC which meets habitability conditions, and which has the space, equipment, supplies, communications and protective means required to fulfill its functions during the various accident conditions (Appendix A, item 11).
The auditors verified that the new revision of procedure IP-1035 provided guidance on evacuating the TSC to the Unit #1 Control Room, although the evaluation of radiological conditions did not include a radiation exposure limit prior to evacuating the TSC.
_,_.
-
,
,
,
.
.
This item will remain open until additional guidance (other than dose rate) is provided in IP-1035 on the allowable exposure prior to evacuating the TSC.
3.12(Closed) 50-003/81-01-16; 50-247/81-06-16 Provisions for a specifically designated, centralized location as Operational Support Center (OSC) supplied with protective means, radiation survey instrumentation, continuous air monitors, means for back-up communications and other equipment needed for the performance of emergency activities that may be required of personnel gathering in the OSC.
(Appendix A, item 12)
The auditors verified that the interim OSC had been relocated to the Administration Building, and that it encompassed the Environmental Health and Safety, and Quality Assurance offices (located in adjacent rooms).
Procedure, IP-1023, specified the number of individuals required to staff the OSC.
Equipment for determining habitability was adequate.
IP-1023 also included provisions for OSC evacuation.
i This item is closed.
3.13 (0 pen) 50-003/81-01-17; 50-247/81-06-17 Provisions for an Emergency Operations Facility (EOF) and alternate EOF having sufficient space, equipment and protective means to enable the direction, coordination and evaluation of all !iceasee's activities during emergency conditions (Appendix A, item 13).
The auditors noted that the licensee made provisions for a temporary EOF in the Buchanan Service Center and a Recovery Center (RC) in the Simulator Building. Procedure CERP-IP-22 indicated when evacuation from these centers was needed, and indicated transfer of control and direction to the Plant Operations Manager (P0M) during evacuation.
The auditors noted, however, that the procedure failed to address how to transfer protective action recommendations during the evacuation of the EOF.
This item will remain open until the procedure includes directions to establish continuity of emergency directive functions.
3.14 (Closed) 50-003/81-01-18; 50-247/81-06-18 Provisions for communication, and protective equipment at the Recovery Center congruent with its expected functions during emergency conditions (Appendix A, item 14).
The licensee had installed additional telephone lines (including hotlines) and survey meters in the recovery center as needed for adequate response during emergency conditions.
This item is close.
,
.
3.15 (Closed) 50-003/81-01-19; 50-247/81-06-19 Revision of the post-accident sampling system to ensure that: the sampling system is functional and safe; the sampling location is accessible during emergency conditions; shielding, tools and instru-mentation for retrieving, transporting and analyzing samples are such that radiation doses to personnel are ALARA (Appendix A, item 15).
The auditors verified that the interim post-accident sampling system had been modified to eliminate the overhead sample line present in the old system, and to reduce the pressure in the sample line during collection. The licensee improved their capabilities for handling, analyzing, and transporting samples, so that it is now feasible to perform these tasks within the ALARA criteria of dose reduction.
This item is closed.
3.16 (Closed) 50-003/81-01-20; 50-247/81-06-20 Provisions for a sampling system for noble gas, radiofodine and parti-culate radioactivity samples from the containment atmosphere that would allow samples to be retrieved, transported and analyzed within three hours of a major accident resulting in ALARA whole body and extremity doses (Appendix A, item 16).
The auditors confirmed that the sample point was changed to another location (the H /0 m nitor cubicle-80-foot level of the-PAB) that 2 2 would be habitable under severe accidents. Maximum exposure rates in
the new sampling area were estimated to be 10 R/hr. A one cm contain-ment atmosphere sample can be collected and diluted 1:3000 prior to analysis. This new sampling facility meets the intent of the ALARA criteria.
This item is closed.
3.17 (Closed) 50-003/81-01-21; 50-247/81-06-21 Provisions for containing the leakage from the present post-accident sampling arrangement for noble gases, and a thorough radiation protection review of the safety and radiation hazards that would be involved in this operation during accident conditions (Appendix A, item 17).
The auditors confirmed the installation of a ventilation hood above the sample collection septum for removing any leakage during the sample collection process.
This item is closed.
I
!
i
.
.
.
.
3.18 (Closed) 50-003/81-01-22; 50-247/81-06-22 i
Using the NUREG-0737 source term as a basis, modification of the vent sampling and analytical system to permit the collection, transportation and analysis of post-accident samples of noble gases, radioiodines and particulates and provision of adequate range survey instrumentation and dosimetry so that whole body and extremity doses would be ALARA (Appendix A, item 18).
The auditors verified the installation of a sampling station for collecting noble gas, radiciodine, and particulate samples from the plant vent at the 98 feet level of the PAB.
Exposure rates were estimated to be 6R/hr, with a 5 min collection time, and meet ALARA criteria.
This item is closed.
3.19 (Closed) 50-003/81-01-23; 50-247/81-06-23 Development of a means for monitoring noble gas releases from the I
plant vent for noble gas concentrations ranging from 8 x 10 uCi/cc-3 to 0.7 uC1/cc.
(Appendix A, item 19).
The auditprs confirmed that the revised procedure made use of a portable radiation survey instrument to detect plant vent concentrations within-3 the 8 x 10 uCi/cc to 0.7 uCi/cc range.
This item is closed.
3.20 (Closed) 50-003/81-01-24; 50-247/81-06-24 Determination of the impact of short-lived noble gases (high energy gamma emitters) on the calibration curve (based on Xe-133) for the extended range plant vent monitor as a function of time following initiation of an accident, and development of a curve or curves, as appropriate, for use in assessment during the early stages of an accident.
(Appendix A, item 20).
The auditors verified the adequacy of the newly developed calibration curves for the interim plant vent monitor, which adjust the detector response to match the softening gamma spectrum.
This item is closed.
3.21 (Closed) 50-003/81-01-27; 50-247/81-06-27 Evaluation of all assembly areas for adequacy regarding location and performance of personnel monitoring and decontamination during accident conditions (Appendix A, item 21).
-_
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
.
.
.
.
The auditors confirmed that procedure IP-1027 was changed to include means for ascertaining the habitability of primary assembly areas.
The auditors determined that instrumentation required was available in these areas.
This item is closed.
3.22 (Closed) 50-003/81-01-28; 50-247/81-06-28 Provision at each assembly area for portable backup lighting, sufficient quantities of dedicated respiratory protection equipment, and protective clothing for all personnel who could be expected to assemble in each assembly area, or provisions to move people out of these areas to other, safe locations (Appendix A, item 22).
The auditors verified that pc-table lighting was provided in all assembly areas, and that sufficient quantities of protective clothing and respirators were available in the Buchanan Service Center.
This item is closed.
3.23 (Closed) 50-003/81-01-31; 50-247/81-06-31 Provision of appropriate stocks of equipment and supplies to enable decontamination of the number of persons that might be expected during emergencies (Appendix A, item 23).
The auditors verified that adequate stocks of equipment and supplies used for personnel decontamination were stored at the Buchanan Service Center.
This item is closed.
3.24 (Closed) 50-003/81-01-33; 50-247/81-06-33 i
Survey of the availability of facilities in the vicinity of the site which could be used for administrative and logistical suppcrt by the expanded support organization in the event of a large scale response to an emergency situation, and incorporation of such facilities into the Emergency Plan and Emergency Procedures Document (Appendix A, item 24).
The auditors verified that the facilities which would be used for administrative and logistical support were identified and incorporated into the CERP.
This item is closed.
k
r
.
.
.
.
3.25(Closed) 50-003/81-01-34; 50-247/81-06-34 i
Provisions for communications and other equipment in the News Center consistent with its designated functions during emergencies (Appendix
'
A, item 25).
During the March 3,1982 emergency exercise of Indian Point Unit 3 the auditors verified that the News Center was provided with telephones, copiers, and recording equipment.
This item is closed.
3.26 (Closed) 50-003/81-01-35; 50-247/81-06-35
"
Provision of additional dedicated equipment (e.g., survey instru-mentation, air samplers, respirators, protective clothing, dosimetry, tools, etc.) within the protected area for:
search and rescue, in-plant surveys, repair and corrective actions, and on-site (out-of-
'
plant) surveys and for assembly / reassembly areas, first aid, and decontamination facilities.
Such equipment shall be strategically located for 1:nmediate use and selected to fit the response needs for the various accident scenarios.
(Appendix A, item 26).
The auditors verified that necessary dedicated instrumentation and equipment were provided for use in:
search and rescue, inplant surveys, repair and corrective action and onsite surveys.
This item is closed.
3.27 (0 pen) 50-003/81-01-36; 50-247/81-06-36 Performance of an engineering study of the existing ARM system to determine the type of upgrading to provide adequate post-accident radiation level mapping capability and to meet the upper limit of
detection (10 R/hr) referenced in ANSI-N320. Upgrade of systems as indicated'by the above study (Appendix A, item 27).
The auditors noted that the licensee was in the process of adding ARMS to the Post-Accident Sampling Area and the High Range Sample Storage Tank Area. A study was in progress to identify other areas which inight benefit from an ARM as an aid in post-accident radiation mapping.
This item will remain open until the above study is completed.
3.28 (Closed) 50-003/81-01-39; 50-247/81-06-39
,
Justification of the location of the existing air bottle refilling station or relocation of the station to an area which would be accessible and could provide quality breathing air during emergency conditions (Appendix A, item 28).
i
.. -
.,
.
_.
.
-.
. -, _ _.
.. - -
. _.
._.
-
-
_.
.
.
.
.
The auditors noted that the licensee made an agreement with the Power Authority of the State of New York (Indian Point Unit 3) to use their equipment and refilling station during an accident at Indian Point Unit 2, and verified that the equipment in both stations was compatible.
This item is closed.
3.29 (Closed) 50-003/81-01-40; 50-247/81-06-40 Provisions for dedicated emergency respiratory protection equipment for all response personnel expected to remain on site during a radio-logical emergency (Appendix A, item 29).
The auditors verified that adequate stocks of respirators in the OSC and control room (backup TSC) were adequate for the number of individuals that would be expected to use them.
This item is closed.
3.30 (Closed) 50-003/81-01-41; 50-247/81-06-41 Provisions to augment the supplies of respiratory protection equipment in the control room to accommodate the necessary personnel from the TSC and OSC, should those facilities become uninhabitable during an emergency.
(Appendix A,. item 30).
The auditors verified that respiratory protection equipment was provided for persons that would relocate from the TSC to the Control Room if the TSC became uninhabitable during an emergency.
This item is closed.
f 3.31 (Closed) 50-003/81-01-44; 50-247/81-06-44 Evaluation of dedicated equipment needs for damage control, corrective action and maintenance, and the positioning of this equipment at specified locations for use during an emergency (Appendix A, item 31).
The auditors verified that the type, amount and location of dedicated equipment for use by the damage control team, was specified after an evaluation of equipment needs.
!
This item is closed.
~
3.32 (Closed) 50-003/81-01-45; 50-247/81-06-45 Evaluation of dedicated materials needed during an emergency, establish-ment of minimum stock levels of those items, and positioning of those supplies and equipment so as to expedite access by personnel for use during an emergency (Appendix A, item 32).
- -
-.
.
.
-
-
-
._
,
,
.
'
.
The auditors verified that a computerized system for assuring that minimum levels of stock are maintained, was in place.
,
This item is closed.
.
3.33 (Closed) 50-003/81-01-47; 50-247/81-06-47 Revision of implementing instructions for each class of accident such that they coordinate and orchestrate the various licensee emergency actions from the perspective of and for use by the licensee's emergency coordinator, i.e., the Plant Operations Manager (Appendix A, item 33).
The auditors confirmed that Implementing Instructions included the Plant Operations Manager's duties, as required.
This item is closed.
3.34 (Closed) 50-003/81-01-48; 50-247/81-06-48 Definition of EALs based on effluent release rates which correspond to a General Emergency (Appendix A, item 34).
The auditors verified that EALs pertaining to effluent releases and corresponding to a General Emergency were added to Table 4-1 of the Emergency Plan and to Section 6 of the relevant Emergency Operating Procedure.
This item is closed.
3.35 (Closed) 50-003/81-01-53; 50-247/81-06-53 Preparation of an overall procedure which orchestrates, from the viewpoint of the emergency coordinator (e.g., Plant Operations Manager)
the licensee's overall accident assessment scheme (Appendix A, item 35).
The auditors verified that the new revisions of the licensee's Imple-menting Instructions contain directions for the emergency coordinator to:
compare predicted offsite exposure rates with field measurements; and orchestrate the overall accident assessment scheme.
This item is closed.
3.36 (Closed) 50-003/81-01-54; 50-247/81-06-54 Revision of the DMR procedure or justification of the discrepancies between DMR and EPA PAG calculations for whole body and thyroid dose projections (Appendix A, item 36).
>
.
..
The auditors reviewed the DMR procedure and verified that discrepancies
,
between this document and the EPA PAG calculations had been corrected.
This item is closed.
3.37 (Closed) 50-003/81-01-61; 50-247/81-06-61 Provision of a procedure for performing in plant surveys in order to evaluate radiological conditions inplant during accidents to include
!
cautions and prerequisites required to deal with unusual plant conditions (Appendix A, item 37).
The auditors verified that a new procedure (IP-1042) addresses inplant surveys, and contains cautions and prerequisites required to deal with unusual plant conditions.
This item is closed.
3.38 (Closed) 50-003/81-01-62; 50-247/81-06-62 Revision of existing procedures (IP-1010, -1011, -1023) to include radiation protection precautions and prerequisites and provisions for pre-task team briefings relative to the radiological conditions to be expected (Appendix A, item 38).
The auditors verified that revision of Procedures IP-1010 and 1011 included adequate radiological protection precautions, prerequisites and briefings.
This item is closed.
3.39(Closed) 50-003/81-01-63; 50-247/81-06-63 Revision of procedure IPC-E-001 to include prerequisites and specific radiological precautions appropriate to post-accident primary coolant sample collection, transport, handling and analyses (Appendix A, item 39).
The auditors verified that licensee prerequisites and radiation protec-tion precautions were added to procedure IPC-E-001.
This item is closed.
3.40 (Closed) 50-003/81-01-68; 50-247/81-06-68 Revision of procedure IPC-E-002 to include prerequisites and specific radiological precautions appropriate to post-accident containment air sample collection, transport, handling and analyses (Appendix A, item 40).
.-
_
_
_
~
.
..
.
.
-13
-
The auditors verified that the licensee added prerequisites and radiation protection precautions to-procedure IPC-E-002.
,
This item is closed.
<
3.41(Closed) 50-003/81-01-69; 50-247/81-06-69 Development of procedures for post-accident containment radioiodine and particulate. sample collection, transport, handling and analyses, consistent with the sampling system to be installed as discussed in Section 4.1.1.6 of this report (Appendix A, item 41).
The auditors _ verified that the Ticensee relocated the sampling station to a location that would be accessible during severe accident conditions and modified procedure IPC-E-002 to allow the collection and analysis of air particulates and radiciodines containment samples.
'
This item is closed.
3.42 (Closed) 50-003/81-01-72; 50-247/81-06-72 h
~
Modifica_ tion of relevant procedures to reflect prerequisites and specific radiation protection requirements which are responsive to post-accident airborne effluent sample collection, transport," handling and analyses in radiation fields commensurate with those predicted by a licensee study, as well as those fields which can be estimated from
'
the NUREG-0737-source term (Appendix A, item 42).
The auditors verified that the licensee added prerequisites and radiation protection precautions to procedure IPC-E-003.
,
This item is closed.
3.43 (Closed) 50-003/81-01-75; 50-247/81-06-75 Modification of Procedure IPC-E-003 to reflect the large amounts of radioactivity on cartridges and filters for post-accident vent sample
!
analyses, or provision of other means and procedures to obtain the above analyses (Appendix A, item 43).
,
'
,
The auditors verified that the licensee relocated the plant vent sample point to an accessible location and significantly reduced the flow rate to permit handling and analysis of the particulate filter and charcoal cartridge.
This item is closed.
,
--.
c
,
- - _ - - _ _. -,
-
-,.,
_
.
~
..
.
-
-
3.44 (Closed) 50-003/81-01-79; 50-247/81-06-79 Development ^of specific and detailed procedures for each of the specific areas of radiation protection as applicable to emergency conditions, incorporating radiation protection guidelines and. instructions, speci-fically delineating each procedures applicability during emergencies, and referencing other appropriate procedures (Appendix A, item 44).
The auditors reviewed new radiation protection procedures and noted that they adequately addressed the intent of this finding.
This item is closed.
'
3.45 (Closed) 50-003/81-01-80; 50-247/81-06-80 Development of a general procedure which governs the overall implementa-
'
tion of the radiation protection program during emergencies; including the priorities demanded by the. logistics of.the various situations, ALARA considerations, and authorization criteria to exceed 10 CFR 20 guidelines for personnel exposure (Appendix A, item 45).
The auditors verified that the new revision of procedure IP-1044 contained adequate references to other procedures (e.g. health physics)
that would be followed during an emergency.
"
This item is closed.
3.46 (Closed) 50-003/81-01-81; 50-247/81-06-81
^
Development of specific and clear action levels to initiate personnel assembly, accountability and evacuation from licensee controlled
'
areas.
(Appendix A, item 46).
The auditors verified that the implementing instructions included action levelt for assembly and evacuati'on from controlled areas, under the directior of the POM.
This item is closed.
3.47 (Closed)50-003'81-01-82; 50-247/81-06-82 Development of specific procedures to govern evacuation and account-ability of personnel for containment evacuation (Appendix A, item 47).
The auditors determined that the revised procedure, HPI 2.28, adequately
, addressed evacuation from containment.
,
.
This item is closed.
-_.
_
-
-
- _.
-. - - - - -
..
,
.
.
3.48 (Closed) 50-003/81-01-84; 50-247/81-06-84 Revision of procedure IP-1027 to include the methods, procedures and forms to be used for performing personnel accountability during the various accident scenarios and to ensure continuing accountability of
'
persons during emergency conditions (Appendix A, item 48).
The auditors determined that revised procedure IP-1027 included an adequate method to perform personnel accountability.
This item is closed.
3.49 (Closed) 50-003/81-01-85; 50-247/81-06-85 Revision of decontamination procedures (i.e., personnel and equipment)-
to address the following:
logistics, information flow, locations of decontaminants and radiological instrumentation, radioiodine deconta-mination, methodology, records of decontamination progress, and the relevancy of further assessment (i.e., bioassays) (Appendix A, item 49).
-
The auditors verified that new revisions of procedures IP-1008, -1009, and -1012 properly addressed the' intent of the findings.
This item is closed.
3.50 (Closed) 50-003/81-01-87; 50-247/81-06-87 Development of specific procedures addressing security under radiological emergency conditions (Appendix A, item 50).
The auditors verified that the licensee had a new procedure covering specific security actions during emergencies such as:
site access for emergency vehicles, issuance of radiological equipment stored at the Guard House, and support of fires involving radioactive materials.
This item is closed.
3.51 (Closed) 50-003/81-01-88; 50-247/81-06-88 Incorporate into IP-1011 specific locations and description of equipment (e.g., radiation detection instruments, tools, etc.); the criteria and logistics of selection of team members; communication means and precau-tions to be employed (Appendix A, item 51).
The auditors verified that the new revision of procedure IP-1011 specified locations and descriptions of equipment, and the criteria and logistics for the selection of team members.
This item is close... -. -
.. _ - - -. -
- - - - ~~
. _ _.
.-
.
..
.
.
3.52 (Closed) 50-003/81-01-89; 50-247/81-06-89 Development of a procedure that will:
identify the organization i
involved in news dissemination, spect fy their location (s) and ways of contacting them, specify the method 'or coordinating the dissemination'
I of information, clearly identify the utility spokesperson and specific
!
sources of information to be used by the utility spokesperson, and provide for rumor control (Appendix n, item 52).
!
The auditors verified that procedure CERP-IP-8, "Public Information",
" -
properly addressed the news center oaganization and responsibilities,
!
facility location and activation, and sources of information to be
,
disseminated.
'
,
This item is closed.
b~
3.'53 (Closed) 50-003/81-01-90; 50-247/81-36-90
,
Revision of inventory and operational check procedures for emergency equipment to include: unambiguous specification of radiation survey i
instrumentation consistent with their intended use; development of procedures for operationally checking the same; and a criterion for acceptance or rejection of instruments (Appendix A, item 53).
l The auditors verified that the new revision of procedure IP-1018
~
included criteria for acceptance and/or rejection of specif1c survey instruments, and that they were listed by model number in the inventory.
This item is closed.
3.54 (Closed) 50-003/81-01-96; 50-247/81-06-96 Establishment of a program for disseminating emergency preparedness information to the public within the plume exposure pathway, including, but not be limited to, information about radiation, contacts for additional information and protective action recommendations, provisions for updating, as necessary, and annually in a form likely to.be available in a residence and public areas (Appendix A, item 54).
The auditors verified that the licensee had established and implemented
-
a program for disseminating emergency preparedness information to the l
public within the plume exposure pathway.
'
This item is closed.
3.L5 (Closed) 50-003/81-01-97; 50-247/81-06-97 Establishment of a familiarization program for the news. media to be conducted annually, including, but not be limited to, provisions for familiarizing the news media with emergency plans, points of contact
'
a
?
i
_
w [-
%
- -.
,
,, - -.
.,-.-
.
- - -
w.---.
.s-
_,, _. --,-
,
, _.,,
. - - -.
p
_
.. - -.
..
. - -
- _ -. - _ -
.
. -
J
.
.
.
J
.
-
.-
for release of public information, and space and equipment allocated for their use (Appendix A, item 55).
The auditors verified that the news media familization program esta-blished and implemented by the licensee contained all the elements
,
necessary to meet the intent of the finding.
-
This item is closed.
i 3.56 (Closed) 50-003/81-01-98; 50-247/81-06-98 Evaluation of the number, locations, equipment adequacy and immediate accessibility, and provision of such equipment and stores to assure
,
their immediate availability for use b. emergency response personnel to' perform their assigned tasks using ALARA principles (Appendix A, item 56).
This item was addressed and closed together with item in Section 3.26.
,
'
-
3.57 (Closed) 50-003/81-01-04; 50-247/81-06-04 Development and implementation of specific selection and qualification criteria for individuals performing emergency preparedness development and maintenance activities (Appendix B, item 1).
,
The auditors verified that a position guide for the Emergency Planning Director had been developed and implemented.
This item is closed.
3.58 (0 pen) 50-003/81-01-05; 50-247/81-06-05 Development of a program for training individuals who are assigned emergency planning responsibilities which will enable them to attain and maintain a state-of-the-art knowledge in the field of emergency preparedness (Appendix B, item 2).
The auditors verified that individuals assigned emergency planning responsibilities were provided with opportunities to attend training programs that will enable them to maintain a state-of-the-art knowledge
-
E as necessary; however, a written program was not in place.
This item will remain open until a written program is in place.
3.59 (Closed) 50-003/81-01-12; 50-247/81-06-12 Revision of the Emergency Plan to clarify and correct training categories so that they are consistent throughout the document (Appendix B, item 3).
.
-.m
- - - ~-
m
-
r
+
-,&--
- - --
_
mc.
.~,y
_
- ~., -,. - -. - - - - - -
w
_ - - -
_ _ _ -_
-
_
_ - -. _ - _ _ - -
_
_
_
_.
.
.
.
The auditors verified that the revised training categories in section 8 of the Emergency Plan were consistent with those in section 14 of the Training Manual.
This item is closed.
3,60 (Closed) 50-003/81-01-14; 50-247/81-06-14 Re-evaluation of plant drawings to ensure that all needed drawings would be readily accessible during accident conditions (Appendix B, item 4).
The auditors verified that the licensee conducted an evaluation of plant drawings available in the control room to determine whether a complete set would be available as needed during emergencies.
This item is closed.
3.61 (Closed) 50-003/81-01-26; 50-247/81-06-26 J
Completion of the calibration of the portable Ge spectrometers and the dedication of one of the two units as a post-accident environmental
'.
sample counting system (e.g., relocating it to the ECC) (Appendix B, item 5).
i The auditors verified that the new revision of procedure IP-1004 provides information on the dedicated locations and requirements for operation of the portable intrinsic germanium spectrometers.
This item is closed.
!
3.62 (Closed) 50-003/81-01-29; 50-247/81-06-29 Designation in the Emergency Plan and the Emergency Procedures Document of all actual assembly / reassembly areas (Appendix B, item 6).
The auditors verified that new revisions of the Emergency Plan and
procedures include all assembly areas.
.
This item is closed.
l 3.63 (Closed) 50-003/81-01-30; 50-247/81-06-30
Provisions for immediate access to all first aid facilities during emergency conditions (Appendix B, item 7).
The auditors veritied that the licensee had installed a sign at each
,
first aid facility to indicate the location of keys.
>
The item is closed.
I
.-
--
-
-
. - -
-
- _ _.
-
-
- - -. - -
-
-
--
-.
..
.
.
.
3.64 (Closed) 50-003/81-01-32; 50-247/81-06-32 Provide copies of necessary Emergency Plan Implementation Procedure IP-1008, IP-1009 and IP-1014 at each location where personnel /
equipment decontamination is expected to take place (Appendix B, item 8).
The auditors verified that necessary procedures were provided at the various decontamination locations.
This item is closed.
3.65 (Closed) 50-003/81-01-37; 50-247/81-06-37 Justification of the positioning of instruments mounted on the primary meteorological tower or relocation of these instruments to conform to Regulatory Guide 1.23 (Appendix B, item 9).
The auditors observed the meteorological tower and the modification records which indicated the instrument arm had been extended as needed.
This item is closed.
3.66 (0 pen) 50-003/81-01-38; 50-247/81-06-38
>
Determination of whether 15-minute averaged data from this tower reasonably represent information from the primary system (i.e., the site meteorology) and if not representative, appropriate modifications to assure the representativeness of the back-up tower data (Appendix B, item 10).
The licensee decided to reactivate the tower that had been used for plant siting rather than to evaluate the representativeness of the present back-up meterological tower data.
This item will remain open until the above action is completed.
3.67 (Closed) 50-003/81-01-42; 50-247/81-06-42 Development and implementation of a method to ensure the availability of at least minimum levels of stocks of protective clothing for emergency l
use (Appendix B, item 11).
!
The auditors verified that a method for assuring a minimum level of protective clothing was in place and that dedicated stock numbers were assigned to some protective clothing stock.
This item is closed.
.
.
.
s
.
.
3.68 (0 pen) 50-003/81-01-42; 50-247/81-06-42 Provision of direct means of communication other than land-line telephone (e.g., radio system) from the ECC to offsite authorities to ensure
capability of communicating protective action recommendations in the event that telephone systems are unuseable (Appendix B, item 12).
The auditors noted that the licensee was in the process of procuring a license fur a radio communication system.
This item will remain open until the above action is completed.
3.69 (0 pen) 50-003/81-01-43; 50-247/81-06-43 Evaluation and any necessary modifications of the facility public address system to ensure that all plant personnel can both hear and
"
understand messages transmitted over the system to all levels of plant operation (Appendix B, item 13).
The auditors noted that the licensee was conducting an evaluation of the public address system and repairing speakers found to be deficient.
This item will remain open until the above action is completed.
3.70 (Closed) 50-003/81-01-44; 50-247/81-06-44 Revision of the Emergency Plan and the Emergency Procedures Document to reflect actual communica-tions systems installed in each emergency response facility (Appendix B, item 14).
The auditors verified that Emergency Plan an'd Emergency Procedures were revised to reflect actual communication systems.
This item is closed.
3.71 (Closed) 50-003/81-01-46; 50-247/81-06-46 Incorporation of specific references in the Emergency Procedures to the appropriate sections of the Emergency Plan and Implementing Pro-cedures to provide quick quidance to the operators in the transition from off-normal conditions to emergency response (Appendix B, item 15).
The auditors verified that Emergency Operating Procedures were modified, to make reference to Emergency Plan Implementing Procedures.
This item is closed.
,
f
.
_
.
.
.
.
3.72 (Closed) 50-003/81-01-49; 50-247/81-06-49 Re-examination of all EALs to assure that initiating conditions are defined as far as practicable in terms of specific, observable parameters which are immediately available in the control room (Appendix B, item 16).
The auditors verified that EALs were revised to meet the intent of this finding.
This item is closed.
3.73 (Closed) 50-003/81-01-50; 50-247/81-06-50 Referencing, in Implementing Procedure IP-1001 and IP-1002, personnel lists of qualified individuals who would be expected to participate in the emergency response (Appendix B, item 17).
The auditors confirmed that the new revision of procedure IP-1001 made reference to Appendix A of the Emergency Plan, which contains a list of personnel qualified for performing the various emergency response functions.
This item is closed.
3.74 (Closed) 50-003/81-01-51; 50-247/81-06-51 Provision of guidance in Procedures IP-1001 and IP-1002 for the Communi-cator, concerning when to refer personnel to the ECC or the Alternate ECC, and clarification of the specific duties of the Communicator during emergencies (Appendix B, item 18).
The auditors verified that new revisions of procedures IP-1001 and IP-1002 directed the Communicator to inform personnel about the emergency classification and initiating conditions.
This item is closed.
3.75 (Closed) 50-003/81-01-52; 50-247/81-06-52 Provision of concise messages for key personnel recalled to the site, so that in addition to class of emergency, they have some understanding of the nature of the emergency (Appendix B, item 19).
The auditors verified that the new revision of procedure IP-1001 included a message to inform key personnel about existing accident conditions.
This item is closed.
a
_
>
-
-
.
3.76 (Closed) 50-003/81-01-55; 50-247/81-06-55 Notation of review and approval dates and revision numbers on each emergency procedure and instruction such that current documents would be readily apparent to each user (Appendix B, item 20).
The auditors verified that each procedure indicated:
revision number.
and date, number of pages, and SNSC review date.
This item is closed.
3.77 (0 pen) 50-003/81-01-56; 50-247/81-06-56 Implementation of the computer program currently under development for analysis of meteorological data and offsite dose projections (Appendix B, item 21).
The auditors confirmed the installation of a computer terminal, for dose calculations, in the control room aled. procedure for its use.
da Training of personnel has not been comple
-
This item will remain open until the above action is completed.
3.78 (Closed ) 50-003/81-01-57; 50-247/81-06-57 Specification in the relevant procedures of the preferred medium to be used for the collection of airborne radioiodine and the conditions for its use (e.g., use of silver zeolite for all inplant samples and for all environmental samples collected in the presence of noble gases)
Appendix B, item 22).
The auditors verified that procedures IP-1015 and IP-1020 specified the use of silver zeolite cartridges for air sampling where field surveys indicated results greater than 40 mrad /hr.
This item is ci ed.
3.79 (Closed' a0-003/81-01-58; 50-247/81-06-58 Provision of guidance in Procedure IP-1015 relative to the final disposition of samples after collection and field counting and specifi-cation of sample identification data to be included with each collected sample (Appendix B, item 23).
The auditors verified that the new revision of procedure IP-1015 provided guidance on sample identification and disposition.
,l
-
This item is closed.
_. - _. _ _
-. __ _
._
-_ -
_ _. _
_ _ _
.
.
-_
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
.
.
.
.
3.80(Closed) 50-003/81-01-59; 50-247/81-06-59 Provision of guidance in Procedure IP-1015 regarding actions to be taken in the event of failure of'the radios used by survey teams (Appendix B, item 24).
The auditors verified that the new revision of procedure IP-1015 provided guidance for survey teams to return to the ECC for another radio if their unit failed while in the field.
This item is closed.
3.81 (Closed) 50-003/81-01-60; 50-247/81-06-60 Revision of Procedure IP-1006 to include a site map as one of the items on the checklist in Section 3.2 for use by the survey teams, and provisions for recording the time of individual radiation measurements on Form 5 (Appendix B, item 25).
The auditors verified that the new revision of procedure IP-1006 included a site map for locating survey points as identified on the data form.
This item is closed.
3.82 (Closed) 50-003/81-01-64; 50-247/81-06-64 Inclusion of a schematic in the Procedure IPC-E-001 to ensure proper valve lineups for post-accident coolant sampling (Appendix B, item 26).
The auditors verified that a map, showing cubicle layouts and valve locations, was added to procedure IPC-E-001.
This item is closed.
3.83 (Closed) 50-003/81-01-65; 50-247/81-0665 Provisions for post-accident coolant sample labeling for identification for any subsequent analyses and disposition.
(Appendix B, item 27).
The auditors verified that labeling requirements were included in procedure IPC-E-001.
This item is closed.
3.84 (Closed) 50-003/81-01-66; 50-247/81-06-66 Specification of reporting requirements for sample results, including reporting time frame (with appropriate time alloted for verification
\\-
.
-
.
.
_.
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
_
_
_;
_
.
.
.
of results) and to which element of the emergency organization the results shall be reported (Appendix B, item 28).
.
The auditors confirmed the addition of a reporting requirement to
-
Procedure IPC-E-001.
This item is closed.
3.85(Closed) 50-003/81-01-67; 50-247/81-06-67 Incorporation of references to the specific sample analysis procedures as part of IPC-E-001 (Appendix B, item 29).
The auditors confirmed that the revised procedure, IPC-E-001, made reference to specific analytical procedures.
This item is closed.
3.86 (Closed) 50-003/81-01-70; 50-247/81-06-70 Specification of reporting requirements for sample results, including
'
reporting time frame (with appropriate time alloted for verification of results) and to which element of the emergency organization the results shall be reported (Appendix B, item 30).
The auditors confirmed the additions of reporting requirements to Procedure IPC-E-001.
This item is closed.
3.87 (Closed) 50-003/81-01-71; 50-247/81-06-71 Incorporation of references to the specific sample analysis procedures as part of IPC-E-002 (Appendix B, item 31).
The auditors verified that the revised procedure IPC-E-002 made reference to appropriate analytical procedures.
This item is closed.
!
3.88 (Closed) 50-003/81-01-73; 50-247/81-06-73 Clarification of Procedure IPC-E-003 to assure that silver zeolite cartridges will be used for post-accident radioiodine sampling from the plant vent (Appendix B, item 32).
The auditors verified that procedure IPC-E-003 clarified the use of
,
silver zeolite cartridges for the collection of radiciodine samples
'
from the plant vent.
This item is closed.
._ _
_
.
.
.
__
_ _ _ _ _ _ _ _ _
_
-
.
.
-
.
.
3.89 (Closed) 50-003/81-01-74; 50-247/81-05-74 l
Provision of a schematic in the Procedure IPC-E-003 to ensure proper valve lineup for post-accident airborne effluent sampling (Appendix B, item 33).
'
The auditors confirmed that a sample system valving schematic was added to procedure IPC-E-003 to ensure proper valve line-ups during the collection of plant vent samples.
This item is closed.
3.90 (Closed) 50-003/81-01-78; 50-247/81-06-78 Revision of Procedure IP-1004 and other relevant procedures to detail the method by which the Emergency Director is to orchestrate the REMP
sample collection and analyses, and to provide, as far as practical, for per planned sample collection frequencies for various magnitudes and modes of activity releases following an accident (Appendix B, item 34).
The auditors confirmed that procedure IP-1004 was revised to indicate when environmental monitoring would be initiated.
This item is closed.
3.91 (Closed) 50-003/81-01-83; 50-247/81-06-83 i
Designation in the procedures of alternate routes for personnel to their assigned assembly areas and criteria for the use of those alternate routes (Appendix B, item 35).
The auditors confirmed that alternate routes to the Buchanan Service Center, and criteria for their use were specified in their procedures.
This item is closed.
3.92 (Closed) 50-003/81-01-86; 50-247/81-06-86 Revision of pertinent procedures to provide descriptions of specific interfaces with and criteria for use of offsite medical facilities (Appendix B, item 36).
The auditors verified that procedure IP-1012 was revised to describe interfaces with offsite medical facilities.
This item is closed.
.
_
_
s-e
.
.
3.93 (Closed) 50-003/81-01-91; 50-247/81-06-91 Provisions for check sources to allow radiation survey instruments to be operationally checked immediately before use (Appendix B, item 37).
The auditors verified that operational check sources were located with i
survey instruments.
This item is closed.
3.94 (Closed) 50-003/81-01-92; 50-247/81-06-92 Incorporation of all drills (including communication drills) and j
exercises referred to in the Emergency Plan into Implementing Procedure IP-1019; specification of who has responsibility for scenario development for each drill; clarification of the titles of Plant Manager and Emergency Planning Coordinator referred to in IP-1019 so that it is consistent with the actual organization structure; and procedural provisions for the participation of offsite agencies in plant drills and exercises (Appendix B, item 38).
The auditors confirmed that the new revision of procedure IP-1019'
included necessary information to meet the intent of the finding.
This item is closed.
3.95 (Closed) 50-003/81-01-93; 50-247/81-06-93
.
Development of cover sheets for the Emergency Plan Implementing Pro-
cedures, which provide, as a minimum, the signatures of appropriate individuals and groups indicating review and approval, and the date of such review, approval and issuance.
The licensee addressed this together with the finding in section 3.76.
This item is closed.
3.96 (Closed) 50-003/81-01-94; 50-247/81-06-94 Coordination of interface with Region I, NRC emergency response organi-zation through the Region I Emergency Preparedness Coordinator (Appendix B, item 39).
The auditors verified that the workspace and communications capability of the interface network, in emergency response facilities, was upgraded to accomodate NRC needs.
This item is closed.
.
.
_-__
_ o..
..
.
.
3.97 (Closed) 50-003/81-01-95; 50-247/81-06-95 Provision of updates of all letters of agreement with offsite support organizations (including PASNY) or ceritication that they are current on an annual basis (Appendix B, item 40).
The auditors verified that the Emergency Plan included up-to-date letters of agreement.
This item is closed.
l
.
I
I i
I J