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#REDIRECT [[RBG-14-819, Responds to Generic Ltr 82-33 Re Suppl 1 to NUREG-0737, Requirements for Emergency Response Capability. Status & Proposed Completion Schedule for Phased Implementation & Integration Plans Encl]]
| number = ML20073J055
| issue date = 04/15/1983
| title = Responds to Generic Ltr 82-33 Re Suppl 1 to NUREG-0737, Requirements for Emergency Response Capability. Status & Proposed Completion Schedule for Phased Implementation & Integration Plans Encl
| author name = Booker J
| author affiliation = GULF STATES UTILITIES CO.
| addressee name = Eisenhut D
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| docket = 05000458, 05000459
| license number =
| contact person =
| case reference number = RTR-NUREG-0737, RTR-NUREG-737, TASK-1.C.1, TASK-1.D.1, TASK-1.D.2, TASK-3.A.1.2, TASK-3.A.2.2, TASK-TM
| document report number = GL-82-3, RBG-14-819, NUDOCS 8304190154
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 12
}}
 
=Text=
{{#Wiki_filter:l
                *                                            ,e GULF STATES                  UTILITIES COMPANY PosToFFICEBOX 2951 *OEAUMONT. TEXAS 77704 AREA CODE 713 838-3631 April 15, 1983 RBG-14,819 File Code G9.33.4, G9.5 Mr. Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555
 
==Dear Mr. Eisenhut:==
 
River Bend Station Units 1 and 2 Docket Nos. 50-458/50-459 Gulf States Utilities Company (GSU) has reviewed Generic
,          Letter 82-33, " Supplement 1 to NUREG-0737-Requirements for Emergency Response Capability," as guidance for the emergency response activities ongoing at River Bend Station (RBS) Units 1 and 2.      GSU has proceeded to implement emergency response activities to meet Nuclear Regulatory Conunission (NRC) requirements. The status and proposed schedule for completing each of the Generic Letter 82-33 items is attached (Attachment 1). A description of GSU's phased implementation and integration plans of the activities is also included (Attachment 2).
GSU understands the concerns of the NRC in establishing realistic plant-specific schedules that take into account the unique aspects of the work at each plant. GSU has developed a RBS plant-specific schedule for each item. GSU will work closely with the RBS NRC Project Manager to reach an agreement <on the final schedules for implementation of these RBS emergency response activities. The information provided herein as agreed to by the NRC will be included in a future amendment to the RBS Final Safety Analysis Report (FSAR). If any of the agreed to dates provided herein should change, a revised schedule and justification for the charge will be provided.
foYL 0304190154 830415 PDR ADOCK 05000458 PDR p
 
e GSU appreciates the NRC's efforts to clarify these issues and establish implementation schedules.
Sincerely,
                                                        !'^~
f f. b J. E. Booker Manager-Engineering, Nuclear Fuels & Licensing River Bend Nuclear Group WJC/RJK/kt Attachment I
r
 
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION STATE OF TEXAS                          I COUNTRY OF JEFFERSON                    1 In the Matter of                        I            Docket Nos. 50-458 50-459 GULF STATES UTILITIES COMPANY            l (River Bend Station, Units 1 and 2)
AFFIDAVIT J. E. Booker, being duly sworn, states that he is Manager-Engineering, Nuclear Fuels, and Licensing: that this position requires him to submit documents to the Nuclear Regulatory Connission in behalf of Gulf States Utilities: that the documents attached hereto
* are true and correct to the best of his knowledge. ~1nfornation and belief.
hf p.E. Booker
                                                            ^
2_
Subscribed and sworn to before me, a Notary Public in and for the State and County above named, this /IM day of                          ,19/g, MJ 0. 8d                    ~ n9 Notary Public in and for      [
Jefferson County, Texas My Commission Expires:
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RBG-14,819 Attachment 1 Page 1 of 5 Response to Generic Letter 82-33 Emergency Response Activities I.D.2 - Safety Parameter Display Console (SPDS)
The River Bend Station (RBS) SPDS consists of three graphic displays located in the Main Control Room.
Technical Support Center (TSC), and Emergency Operations Facility (EOF). With exception to the Digital Radiation Monitoring System (DRMS) meteorological and radiological displays, GSU's SPDS will be supplied by General Electric Company (GE) as part of the Nuclear Steam Supply System (NSSS) scope of supply. GE has completed the hardware design and is presently finalizing the system software. The RBS SPDS configuration (safety analysis) was based upon a study documented in NUREG/CR-2100, the Symptom-Oriented Emergency Procedure Guidelines developed by the Boiling Water Reactor Owners' Group (BWROG), and Regulatory Guide (R.G.) 1.97, Rev. 2, " Instrumentation For Light-Water-Cooled Nuclear Power Plancs To Assess Plant And Environs Conditions During And Following An Accident". The GE designed SPDS graphic displays for RBS will be similar to those supplied to Cleveland 1 Electric Illuminating Company's Perry Nuclear Power Plant. GSU will review the NRC's post-implementation review for the Perry SPDS.
Therefore, GSU will not request the NRC's optional pre-implementation review for RBS.
Since the software design has not yet been completed by GE, GSU cannot provide a schedule for the SPDS implementation plan at this time. The implementation plan, including the submittal date for the SPDS safety analysis, will be provided in August, 1983. Currently, it is estimated that GSU's SPDS training program plan will be completed approximately one year prior to the fuel load date. Figure 2 shows the integrated network for the SPDS with other related activities.
I.D.1 - Detailed Control Room Design Review (DCRDR)
GSU has been actively participating with industry committees including the BWROG Control Room Committee and the Nuclear Utility Task Action Committee (NUTAC) for Emergency Response Capabilities in developing a generic approach for performing a DCRDR. A partial DCRDR was conducted on the Unit 1 main control room at GE's San Jose, California facility during staging prior to shipment to the site. This partial DCRDR was based on the BWROG control room survey plan. The survey was performed to identify any major design improvements
 
RBG-14,819 Attachment 1 Page 2 of 5 during the early stages of testing following the initial design and fabrication.
Areas such as maintenance, surveillance, training, and manning will be performed during the final DCRDR. The results of the partial DCRDR and a checklist of items will be included in the final review.
The RBS DCRDR program is based on industry guidance documents such as NUREG-0700, NUREG-0801, and the BWROG control room survey. A program plan and schedule will be provided sixteen months prior to fuel load (see Figure 1). After submittal of the program plan, GSU will begin the review to identify any human engineering discrepancies (HED). Following this review, safety implications of the HED's will be analyzed and any necessary corrective actions will be addressed. A schedule for implementation of required modifications to the main control room will be developed. A summary report will be submitted six months prior to fuel load, which describes the review findings and scheduled implementation dates for modificacions.
Changes to the main control room design will be reflected in GSU's training program for the licensed operators. Figure 2 shows the integrated network for the DCRDR with other related activities.
Regulatory Guide 1.97, Rev. 2 - Application to Emergency Response Facilities GSU has reviewed R.G. 1.97, Rev. 2, criteria and has incorporated the indication of appropriate variables in the main control room to ensure that necessary information is available to the plant operator to help prevent and mitigate consequences of reactor accidents / transients. The RBS position on R.G. 1.97, Rev. 2 is provided in Section 1.8 of the FSAR. Tables 7.5-1 and 7.5-2 in the FSAR provide information for each type A, B, C, D and E variable. A schedule and additional information concerning the environmental and seismic qualification criteria, redundancy and sensor locations, type of power supply, and location of display will be submitted by fuel load. Integration of R.G.
1.97, Rev. 2 is shown on Figure 2.
I.C.1 - Guidance for the Evaluation and Development of Emergency Operating Procedures (EOP) for Transients and Accidents Currently, RBS is using the BWROG Emergency Procedures Guidelines (EPG) Revision 3 as its technical guidelines for developing plant specific Emergency Operating
 
RBG-14,819 Attachment 1 Page 3 of 5 Procedures (EOP). Revision 3 of the BWROG EPG's was submitted to the Nuclear Regulatory Commission on December 22, 1982, in a letter from Tom Dente,' Chairman, BWR Owncrs' Group, to D. G. Eisenhut, Director, Nuclear Reactor Regulations (NRR). Therefore, no additional GSU technical guideline submittal will be made. The draft RBS E0P Writer's Guide is being developed in accordance with INPO operating procedure writing guidelines. The calculations to determine plant specific values for inclusion in the EPG's are being performed by GE. GSU is developing the E0P verification and validation program in accordance with INPO guidelines.
The RBS Procedures Generation Package will be submitted to the NRC by August, 1983. The E0P's will be integrated into the operator cold license training program. It is anticipated that the cold license training will begin in October of 1983. The RBS Training Program Plan is estimated to be complete one year prior to fuel load.
E0P's will be available for plant operation when the RBS Operating License is issued. The currant RBS Fuel Load date is April, 1985.
III.A.1.2 - Upgrade Emergency Support Facilities:
The RBS emergency response facilities (ERF) serve to provide a coordinated group of facilities to enhance management of accident conditions. The ERF's are physically separated to minimize interference and confusion. Each facility is connected by dedicated communication lines to ensure an uninterrupted flow of i data and instructions.
o    Technical Support Center (TSC)
A description of GSU's TSC, is given in the FSAR Section l
13.3.6.1.1, and Figure 13.3-20 in the FSAR provides the floor plan of the TSC.
; The TSC will be located in the Services Building.
! Construction of the Services Building began in early l 1983. At this time, the design specifications for the TSC have not been finalized. GSU's projected completion j date for a fully functional TSC (i.e., structure, l inscrumentation, procedures, and trained staff) is
; anticipated to be ten months after the fuel load date or l spproximately two months after commercial operation.
1 L
 
RBG-14,819 Attachment 1 Page 4 of 5 o    Operational Support Center (OSC)
Section. 13.3.6.1.2 of the FSAR provides a description of the OSC.
The OSC will be located in the Services Building. The floor plan is shown in Figure 13.3-21 of the FSAR.
The RBS Services Building is currently under construction. A fully functional OSC is anticipated to be complete two (2) months after the fuel load date and prior to commercial operation.
o    Emergency Operating Facility (EOF)
FSAR Section 13.3.6.1.5 describes the EOF and its backup facility.
The structural design and construction of the RBS EOF are complete. Internal facility design has not been ffaalized. GSU anticipates that the EOF will be fully functional ten months after fuel load or approximately
  -  two nonths after Commercial Operation.
EOF coordination with non-utility participation is described in Section 13.3.6.1.5.2 of the RBS FSAR.
III.A.2.2 - Meteorological Data RBS employs a Digital Radiation Monitoring System (DRMS) with the capability to assess radiological conditions i    during normal and abnormal operating conditions. The I      offsite dose assessment portion of the DRMS will display the meteorological data recommended by Regulatory Guide 1.97, Rev. 2. Meteorological displays will be available l
in the TSC and EOF only. The system design is complete and has been procured. GSU anticipates that the system l,    will be delivered by November, 1984 and will be fully functional in the TSC and EOF ten months after the fuel load date or appproximately two months after Commercial Operation.
Emergency Response Training Program GSU's emergency response integrated training program is
!      in its developmental stages. Activities related to emergency response capability will be considered for inclusion in the training program plan. RBS's training program plan is anticipated to be complete one year prior to fuel load. At that time GSU will have an integrated training plan which includes SPDS, DCRDR, E0P, R.G.-1.97, Rev. 2, and ERF's.
[
 
RBG-14,819 Attachment 1 Page 5 of 5 4
Schedule Summary Based on the Fuel Load i                                                            Date of April, 1985
)                                                            SPDS Implementation Plan,. Operability                  August, 1983 Schedule, & Safety Analysis E0P Generation' Package                                August, 1983 l                                                            DCRDR Program Plan                                  . January, 1984 Training Program Plan Developed                          April, 1984 DCRDR Summary Report                                    October, 1984 f
R.G. 1.97, Rev. 2 Report                                April, 1985 Emergency Response Facilities                          February, 1986
-                                                        - Fully Functional I
: a. DRMS                                        February, 1986
!                                                            Verification and Validation Process                    Sune.er , 1986                                                              ,
Complete 1
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RBG-14,819 Attachment 2-Page 1 of 2 Discussion of the Coordination and Integration of Initiatives for River Bend Station GSU developed a plant-specific program, which is shown in Figure 2 (attached). In developing this plan for Emergency Response Capabilities (ERC), GSU used Guidance for an Integrated ERC Implementation Plan, that was developed by the Nuclear Utility Task Action Committee (NUTAC).
Figure 2 is divided into seven basic steps that will be considered in the development of an integratad plant-specific implementation plan. For the remaining work, each step and its relation to previous and succeeding steps is discussed in the following plan descriptions.
A. E0P Plan The E0P plan consists of tasks that will provide a documented method for developing, utilizing, revising, and controlling Emergency Operating Procedures.
This plan will include definition of source documents, determination of manpower requirements, establishment of a schedule, and specification of the method of document control. This plan also defines the interfaces with other NUREG-0737, Supplement 1 elements to ensure complete integration.
;      Initial plant-specific E0Ps will be developed by GSU for the purpose of mitigating the consequences of a broad range of initiating events and subsequent multiple failures or operator errors, without the need to diagnose a specific event. These procedures'will be symptom-oriented and will be written with human factors I      considerations to improve human reliability. The initial E0Ps will be developed based upon the Writer Guide and BWR Owners' Group Emergency Procedure Guidelines.
Determination of procedure adequacy is dependent upon the trained operator's needs. E0Ps will be checked for completeness, understandability, technical correctness, usability, and compatibility with the control room. For operators to have confidence in the E0Ps, all of these criteria will be met. A walk-through in the RBS simulator of the initial E0Ps will provide the method of
;      evaluating these criteria.      Although Figure 1 indicates only one E0P walk-through, additional walk-throughs will be performed as necessary following any major modifications to the E0Ps.
 
RBG-14,819 Attachment 2 Page 2 of 2 B. DCRDR Plan A partial DCRDR was performed by the BWROG. At this time, GSU is following the activities of the DCRDR NUTAC, which is expected to complete its work in September, 1983. Upon finalization of the DCRDR NUTAC recommendations, GSU will evaluate the recommendations and consider them in the development of our detailed program plan.
C. R.G. 1.97 Plan A review has been performed comparing the existing post-
, accident monitoring instruments with that of R.G. 1,97, Rev. 2.
D. Integration Of All Control Room Elements When the DCRDR progran plan has been completed, and the subsequent review performed, the results will be evaluated along with other control room elements. A determination will then be made as to how to correct any identified deficiency. This may be in the form of a revised EOP, a modification to the control room, or a modification to the SPDS.
Once this determination has been made, final E0Ps will be written, final control room modifications will be designed if necessary, and a training program plan based on the above elements with proper objectives, performance evaluations, and revision elements will be developed.
E. Verification and Validation After completing the Verification & Validation (V&V) activities, a report documenting the V&V offort will be developed. Improvements or modifications identified as a result of the V&V efforts will be reviewed to I determine the impact on performance of other emergency response activities. GSU currently projects this
; process will be completed prior to startup at conclusion i of the first refueling (Summer, 1986).
l l
f i
 
SCHEDULE FOR ITEM I.D.1 PHASE I                                                                            PHASE IV PROGRAM PLAN            PHASE II & III                                       
 
==SUMMARY==
REPORT &
SUDtfITTAL          DCRDR & EVALUATION                                          IMTLEMENTATION SUBMIT                                        GSU                          NRC F ROGRAri                                    SUMt1ARY        NRC          SITE            ISSUE          FUEL PLFH                                        REPORT      DECISION          VISIT            SER            LOAD            CO l                                            l          TO VISIT          I                I            I                I i            11 ho.                          I    2 Wks.    !    2 Uks. I      i No. l    6 Mo.          8 Mo.
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