ML20116D482

Comprehensive Action List

ML20116D482
Person / Time
Site:	Comanche Peak
Issue date:	04/30/1985
From:	TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:
Shared Package
ML20116D471	List: ML20116D482 TXX-4467, Forwards Comprehensive Action List in Response to Request for Rept on yet-to-be-completed Work Items for Licensing of Facility
References
NUDOCS 8504290424
Download: ML20116D482 (175)

Text

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.e COMPREHENSIVE ACTION LIST [ CAL]

FOR THE LICENSING OF COM ANCHE PEAK STEAM ELECTRIC STATION l

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CPSES/ CAL PREFACE Texas Utilities Generating Company has completed an examination of the licensing status of the Comanche Peak Steam Electric Station. The purpose of this examination was to compile a single, comprehensive document that addresses all of the yet-to-be completed work items which relate to licensing requirements or commitments for Unit 1 of the Comanche Peak Steam Electric Station.

,This resulting document, the Comprehensive Action List (CAL), identifies and describes the items or activities which, in our judgement, need to be successfully completed or resolved to license CPSES Unit 1.

Items that might need to be,ndividually tracked or followed are identified and described in detail. Each of these items is further categorized (as appropriate) as to its relevance to selected milestone events, such as fuel load, low power testing (5 percent power), and full power operation. The perspective provided by this categorization accurately depicts the actual status of the entire CPSES project.

By its nature, this Comprehensive Action List is a detailed report of the licensing status of CPSES Unit 1 at a point in time, i.e.,

essentially April 15, 1985. Completion of action items is an ongoing process and many items will have been completed during the weeks after April 15, 1985.

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TABLE OF CONTENTS 1: O l

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CPSES/ CAL TABLE OF CONTENTS O

.Section Title Page PREFACE i

TABLE OF CONTENTS ii LIST OF TABLES v

EXECUTIVE

SUMMARY

1

1.0 INTRODUCTION

1-1 2.0 COMANCHE PEAK RESPONSE TEAM 2-1

2.1 INTRODUCTION

2-1

2.2 CONCLUSION

S 2-1 3.0 ATOMIC SAFETY AND LICENSING BOARD 3-1 O

4.0 INDEPENDENT ASSESSMENT PROGRAM 4-1

4.1 INTRODUCTION

4-1 4.2-ACTION ITEMS 4-1

4.3 CONCLUSION

S 4-1 5.0 SAFETY EVALUATION REPORT 5-1

5.1 INTRODUCTION

5-1 5.2 ACTION ITEMS 5-1 5.2.1 OUTSTANDING ISSUES 5-1 5.2.2 CONFIRMATORY ISSUES 5-1 5.2.3 LICENSE CONDITIONS 5-2 5.2.4 OPEN CORRESPONDENCE 5-2

5.3 CONCLUSION

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CPSES/ CAL 6.0 ENGINEERING AND CONSTRUCTION 6-1 0

6.' l INTRODUCTION 6-1 6.2 ACTION ITEMS 6-1 6.2.1-SIGNIFICANT ITEMS 6-1 6.2.2 MASTER DATA SYSTEM RESOLUTION 6-2 6.2.3 SIGNIFICANT DEFICIENCY ANALYSIS REPORTS 6-2

6.3 CONCLUSION

S 6-2 7.0 INSPECTION REPORTS 7-1

7.1 INTRODUCTION

7-1 7.2 ACTION ITEMS 7-1

7.3 CONCLUSION

S 7-1 8.0 PRE 0PERATIONAL TESTING 8-1

8.1 INTRODUCTION

8-1 8.2 ACTION ITEMS 8-1

8.3 CONCLUSION

S 8-1 9.0 OPERATIONS 9-1

9.1 INTRODUCTION

9-1 9.2 ACTION ITEMS 9-1 9.2.1 OPERATIONS PHASE PROGRAMS 9-1 9.2.2 PRE-FUEL LOAD REVIEWS 9-1

9.3 CONCLUSION

S 9-2 10.0 TECHNICAL SPECIFICATIONS 10-1

10.1 INTRODUCTION

10-1 10.2 ACTION ITEMS 10-1

10.3 CONCLUSION

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CPSES/CA.L 11.0 MISCELLANE0US 11-1 0

11.1 INTRODUCTION

11-1

.11.2 ACTION ITEMS 11-1

11.3 CONCLUSION

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CPSES/ CAL LIST OF TABLES 4

x_.s Table Title 4-1 Independent Assessment Program (8 Sheets) 5-1 SER Outstanding Issues (11 Sheets) 5-2

'SER Confirmatory Issues (7 Sheets) 5-3 SER License Conditions (12 Sheets) 5-4 Open Correspondence (4 Sheats) 6-1 Significant Engineering and Construction Items (34 Sheets) 6-2 Significant Deficiency Analysis Reports (7 Sheets)

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7-1 Inspection Reports (35 Sheets) 8-1 Preoperational Tests (16 Sheets) 10-1 Technical Specification Items (3 Sheets) 11-1 Miscellaneous Activities (3 Sheets) n.

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CPSES/ CAL EXECUTIVE

SUMMARY

'O COMPREHENSIVE ACTION LIST (CAL) i e

i FOR THE LICENSING 0F COMANCHE PEAK STEAM ELECTRIC STATION UNIT 1 INTRODUCTION i

The Comprehensive Action List (CAL) tabulates the yet-to-be completed work items (action items) for the Comanche Peak Steam Electric Station (CPSES) Unit 1.

Texas Utilities Generating Company (TUGCO) compiled the

' CAL to provide in a single document a complete identification of the items that need to be resolved to license CPSES Unit 1.

The CAL is based on the status of CPSES Unit 1 as of April 15, 1985.

TUGC0 has included in the CAL those items requiring action by TUGC0 as well as those items awaiting action by the NRC.

I The CAL was compiled from numerous sources such ai Supplemental Safety l

Evaluation Reports (SSERs), licensing correspondence files, inspection report files, nonconformance reports, TUGC0 tracking lists, etc. Each i

source was screened to identify action items for inclusion in the CAL.

The screening process was used to identify open items that have s nif c fort o e,

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m e than about 30 days to complete), or are an unresolved licensing issue i

(e.g., an SER issue that requires TUGC0 or NRC action prior to fuel load). Minor housekeeping, record keeping or routine items that have little potential for impacting schedule or resource commitments have not been individually described in the CAL, but are addressed in a more j

general manner in the appropriate chapters.

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CPSES/ CAL TUGC0 has organized the action items into the following 10 major subject areas to cover the appropriate licensing and functional aspects of the project:

Comanche Peak Response Team Atomic Safety and Licensing Board Independent Assessment Program Safety Evaluation Report Engineering and Construction Inspection Reports Preoperational Testing Operations Technical Specifications Miscellaneous The following information, as applicable, is provided for each identified action item:

A description of each action item; A discussion of the work being done or a plan to resolve an issue satisfactorily or to accomplish successful completion of the item; An estimated completion date for each item; A discussion of tne relationship of each item to major milestone events (fuel load, initial criticality, 5 percent power, and full power operation); and An indication of the safety significance of each action item.

O CPSES/ CAL

SUMMARY

qV COMANCHE PEr.K RESPONSE TEAM The Comanche Peak Response Team (CPRT) is addressing those action items identified by the NRC Technical Review Team. The CPRT is developing a Program Plan and issue specific Action Plans. These detailed plans are being submitted to the NRC staff via separate correspondence and are not described in the CAL.

ATOMIC SAFETY AND LICENSING BOARD Board proceedings are currently suspended pending the completion of certain CPRT plans and staff review of those efforts. The number, nature and scope of pending Contention 5 sub-issues that will require a litigated resolution cannot be determined until after the CPRT action plans have been developed.

O INDEPENDENT ASSESSMENT PROGRAM Several action items have resulted from the Independent Assessment Program (IAP) being conducted by Cygna Energy Services.

Issues raised in the IAP are being incorporated into selected CPRT Action Plans. The CPRT program will resolve the IAP action items. For this reason, individual IAP action items are not described in detail in the CAL.

1 SAFETY EVALUATION REPORT The Safety Evaluation Report (SER) action items (exclusive of CPRT and IAP issues) include yet-to-be completed items or unresolved issues belonging to the following four categories:

Outstanding Issues Confirmatory Issues License Conditions Open Correspondence l

CPSES/ CAL Currently 30 action items associated with 27 issues are addressed. All V

of these items are well-defined. TUGC0 input to the NRC staff is being provided as expeditiously as possible to ensure that none of these items adversely affects licensing decisions or schedule. About 8 issues require additional TUGC0 input.

All defined TUGC0 actions on SER items are expected to be completed by July 1, 1985. Pending favorable staff review of these submittals and of the it'eme rurrently undergoing staff review, neither fuel load nor subsequent operation is constrained by any of the SER action items.

ENGINEERING AND CONSTRUCTION Since early January 1985, TUGC0 nas been providing the NRC staff with periodic updates of.the status of significant engineering and construction action items. The term "significant" means work is

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necessary to meet a licensing requirement or commitment and the item is not a minor work item. Currently, there are 33 action items that are l*

O ciassified as sienificant enoieeerin, and construction work items.

These items involve various TUGC0 activities, such as analysis, design work, equipment installation, modification, replacement or testing and equipment qualification.

Most of the engineering and construction action items are currently scheduled to be completed within the next three months.

None of them is expected to be a constraint to fuel load.

A discussion of six open Significant Deficiency Analysis Reports (SDARs) is also included under the Engineering and Construction action item heading.

Three of these SDARs will be closed by completion of one or more of the 33 engineering and construction action items discussed above. The remaining three items are minor work efforts that will be completed within the next 30 days. Establishment of a fuel load date is not dependent upon closure of the six SDAR action items.

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INSPECTION REPORTS I,_l

%j TUGC0's action item list of open Region IV Inspection Reports currently contains 34 items. This list does not include items for which the only remaining action is reinspection by the NRC staff to close out the inspection report. Eleven of the open inspection report items pertain to issues that are being evaluated by the Comanche Peak Response Team.

Thirteen of the inspection report action items require revision of existing procedures or development of additional procedures. All of these items are scheduled to be completed within the next two months.

Five inspection report action items are also engineering and construction action items and two inspection report items are SER issues.

None of the inspection report items that require reinspection by the NRC, or items that pertain to procedures, engineering and construction or SER issues are of a nature that either individually or collectively are a significant constraint to fuel load and subsequent low power nU operation. Satisfactory closure of most of these items is expected to occur within the next two months.

Inspection report action items that are being addressed in issue specific Action Plans of the Comanche Peak Response Team will be resolved on a schedule consistent with the respective Action Plans.

PRE 0PERATIONAL TESTING Fifteen preoperational tests or verifications remain as action items. A performance schedule has been established for seven of the preoperational tests.

Scheduling of the remaining tests is dependent upon one or more factors, such as completion of engineering and construction items, allocation of manpower resources, and establishment of a fuel load date. The yet-to-be completed preoperational tests will be done prior to fuel load or a justification for deferral will be provided to the NRC.

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i CPSES/ CAL OPERATIONS i lm\\

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Administrative and technical operations phase programs have undergone all internal and external reviews and are currently in place and functioning. There are currently no significant operational phase programs or work items that would adversely affect the ability to load fuel and safely operate CPSES Unit 1.

Any,new work items affecting plant operations that are identified as part of the ongoing plant inspections or reviews will be resolved as they occur using existing administrative and technical programs.

Prior to fuel load, final pre-fuel load reviews will be performed by the Station Operations Review Committee and the Operations Review Committee to confirm operational readiness to load fuel and proceed with subsequent low power testing and commercial operation.

TECHNICAL SPECIFICATIONS 0d The CPSES Final Draft Technical Snecifications were issued on September 4, 1984, and subsequently have been undergoing review by TUGC0 and the NRC staff to ensure completeness. To date, this joint review has resulted in the submittal by TUGC0 of a set of proposed changes to the Technical Specifications, and the submittal by TUGC0 of responses to staff questions.

Staff evaluation of these submittals constitutes the two significant action items pertaining to the Technical Specifications.

Review of the Technical Specifications is an ongoing process and further G anges may be recommended by TUGCU or by the staff; however, the review process is essentially complete. Neither fuel load nor subsequent low power testing is constrained by the action items pertaining to the Technical Specifications. An Affirmation of Correctness of the Unit 1 Technical Specifications will be submitted to the NRC prior to the issuance of the Operating License.

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CPSES/ CAL l

MISCELLANE0US Miscellaneous action items pertain to the Environmental Protection Plan and implementation of the Emergency Plan. TUGC0 has provided comments i

to the staff on the Draft Environmental Protection Plan for CPSES and the only remaining action item is for the NRC to issue the Final Environmental Protection Plan.as Appendix B to the Operating License, i

There are seven outstanding items on the Emergency Plan. All of these items are minor in nature and will be completed before August 1985.

I None of these items will prevent TUGC0 from implementing the Emergency Plan, which has been successfully exercised twice.

CONCLUSIONS The Comprehensive Action List is a compilation of the current status of i

yet-to-be completed work items which relate to the licensing of CPSES l

Unit 1.

Mechanisms are in place to track these action items and work is proceeding in a systematic manner to resolve these items.

i Comanche Peak Response Team action items include the finalization of the i

i Program Plan and the issue specific Action Plans. Resolution of the a

remaining Independent Assessment Program issues is being incorporated I

into the CPRT program. Future Atomic Safety and Licensing Board actions i

cannot be determined until after the CPRT action plans have been s

developed. As presently perceived, action items in the CPRT/IAP/ASLB l

process have direct and significant bearing upon the licensing schedule for CPSES Unit 1.

Although action items exist in the seven other categories presented in the CAL, these items are not perceived as l

contraints to the establishment of a fuel load date or to the granting j

l of a full power Operating License for CPSES Unit 1.

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CPSES/ CAL

1.0 INTRODUCTION

This Comprehensive Action List (CAL) is a report on the status of yet-to-be completed work items (action items) in the total licensing process for Unit 1 of the Comanche Peak Steam Electric Station (CPSES). The CAL identifies action items that were incomplete or unresolved as of April 15, 1985. Work items completed and approved prior to the compilation are not included in the CAL.

Items completed by TUGC0 and submitted to the NRC, i.e., those items awaiting action by the NRC, are included in the CAL as action items.

The CAL was compiled from numerous sources such as SSERs, licensing correspondence files, inspection reports files, nonconformance reports, and various lists used by TUGC0 to track the status of work item categories and individual work items.

Each of these sources was screened to identify action items for inclusion in the CAL, For the most part, the screening process was fq kJ used to identify open items that (1) have potential for affecting the licensing schedule (i.e., items that require a significant work effort to complete, or are projected to take more than about 30 days to complete), and (2) are licensing commitments (e.g., SER issues for which commitments have Deen made to close certain items prior to fuel load). Minor housekeeping, record keeping or routine items that have little potential for impacting schedule or resource commitments have not been individually descrioed in the CAL out are addressed in a more general manner in the appropriate chapters.

The CAL was compiled to provide in a single document a complete identification of action items that need to be completed to satisfy licensing commitments or requirements for the licensing of CPSES Unit 1.

For each action item identified, this compilation also provides, as appropriate, the following itformation:

1.

A description of each action item; 1-1

CPSES/ CAL 2.

A discussion of the work being done or a plan to resolve an issue satisfactorily or to accomplish successful completion of the item; 3.

An estimated completion date for each item; 4.

A discussion of the relationship of each item to major milestone events (fuel load, initial criticality, 5 percent power, and full power operation); and S.

An indication of the safety significance of each action item.

The action items are organized under 10 major subject areas that cover the appropriate licensing activities and the functional aspects of the project (i.e., engineering and construction, startup, and operations).

In some cases there is considerable overlap of specific action items among several of the major subject areas; where this occurs, the action item is fully discussed under one topic but listed under other b) applicable topics and cross-referenced to the location (s) in the CAL v

where the full discussion is provided. The major topics and the types of action items that are described under each topic are as follows:

COMANCHE PEAK RESPONSE TEAM (CHAPTER 2.0)

Inspection reports and recommendations from the NRC Technical Review Team (TRT) have resulted in the formation of a Comanche Peak Response Team (CPRT) that is addressing issues raised Dy the Technical Review Team inspection.

The CPRT, which includes third-party technical specialists and consultants under the direction of a Senior Review Team (SRT) composed of senior TUGC0 line management and senior nuclear industry consultants, has developed a Program Plan and numerous individual detailed issue-Specific Action Plans to resolve the Technical Review Team inspection items. The Response Team's work package, including the Program Plan and the issue-Specific Action Plans, is oeing 1-2

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CPSES/ CAL i

i submitted separately to the NRC ft, review. A discussion of the CPRT program is presented in this chapter.

ATOMIC SAFETY AND LICENSING BOARD (ASLB) (CHAPTER 3.0) i The status of the ASLB hearing process for CPSES is described in this l

I chapter.

INDEPENDENT ASSESSMENT PROGRAM (CHAPTER 4.0)

Action items that require resolution as a result of the Independent Assessment Program Deing conducted by Cygna Energy Services are discussed in this chapter.

SAFETY EVALUATION REPORT (SER) ISSUES (CHAPTER 5.0) l

-UnresoIved licensing issues identified in the CPSES SER or in a later Supplemental Safety Evaluation Report (SSER), excluding NRC Technical Q

Review Team issues (Chapter 2.0) and the Independent Assessment Program (Ct. apter 4.0), are described in this chapter. 'Also included are unresolved action items that originated from NRR correspondence (specific letters to Texas Utilities and generic letters). These action items can De placed conveniently in the following four j

categories:

Outstanding issues Confirmatory issues License conditions Open correspondence i

ENGINEERING AND CONSTRUCTION (CHAPTER 6.0)

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i Since early January 1985, TUGC0 has been providing NRR with periodic f

updates of engineering and construction action items and schedules for

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completion of these items. This CAL chapter contains a discussion of Q

the status of the engineering and construction action items from these I

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CPSES/ CAL periodic updates. These action items are derived from many sources, including:

- Non-conformance Reports Significant Deficiency Analysis Reports

- Test Deficiency Reports Reportable Deficiency Items (10CFR50.5Se)

INSPECTION REPORTS (CHAPTER 7.0)

Unresolved items resulting from Region IV inspections and Inspection and Enforcement Bulletins and Notices are addressed in this chapter.

PRE 0PERATIONAL TESTING (CHAPTER 8.0)

Preoperational tests that are not complete are identified in this chapter.

Certain preoperational tests may be deferred beyond fuel load with NRC approval.

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OPERATIONS (CHAPTER 9.0)

The status of operational readiness is described in this chapter.

TECHNICAL SPECIFICATIONS (CHAPTER 10.0)

Draft Technical Specifications for CPSES Unit I have been issued by the NRC.

TUGC0 and an independent contractor have conducted a comprehensive review of the operating technical specifications.

The unfinished work items resulting fro,n this review and the NRC examination of the technical specifications are discussed in this chapter.

MISCELLANEOUS (CHAPTER 11.0)

Action items not addressed in the preceeding chapters or that do not f]

corveniently fall within the topics of those chapters are contained in 1-4

CPSES/ cad the " miscellaneous" chapter. These items include actions pertaining g

to the Environmental Protection Plan and the Emergency Plan.

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CPSES/ CAL

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2.0 COMANCHE PEAK RESPONSE TEAM

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2.1 INTRODUCTION

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The NRC Technical Review Team (TRT) has identified a number of potential f

open items relating to CPSES which have been transmitted to TUGC0 in l

various documents, including SSERs. To respond to these items TUGC0 has l

established the Comanche Peak Response Team (CPRT). The work of this team has been to develop a Program Plan and Issue-Specific Action Plans to address the concerns identified by the TRT and to direct the activities of various task teams to bring about a timely resolution of l

each issue. A Senior Review Team (SRT) consisting of TUGC0 senior line l

management and independent experts contracted by TUGC0 has been I

established to oversee the actions of the CPRT to assure that each issue l

is resolved satisfactorily.

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The CPRT Program Plan and Issue-Specific Action Plans covering these issues are being submitted separately.

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2.2 CONCLUSION

TUGC0 has launched a significant effort to resolve the NRC Technical Review Team items. The effort is designed to address specific problems as well as the broader potential implications of the items. TUGC0 is F

interfacing with the NRC to clarify issues and is using experts from l

outside TUEC to oroaden its perspective on the issues and the TUGC0 responses.

For many items, resolution has been determined and the actions required to close the item are clearly defined.

Review, inspection and investigation continues on the other items by the dedicated resources assembled by TUGCO.

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CPSES/ CAL 3.0 ATOMIC SAFETY AND LICENSING BOARD Board proceedings are currently suspended pending the completion of certain Comanche Peak Response Team plans and staff review of those efforts. The number, nature, and scope of pending Contention 5 sub-issues that will require a litigated resolution cannot be determined until after the CPRT action plans have Deen developed.

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CPSES/ CAL 4.0 INDEPENDENT ASSESSMENT PROGRAM O

4.1 INTRODUCTION

In March 1983, the NRC directed the applicant to hire an outside consultant to conduct an independent assessment of the Comanche Peak design. A program was developed and a consultant, Cygna Energy Services, was selected to carry out this program.

Initially, the program consisted of two phases; Phase I relating to design control and the spent fuel pool cooling system and Phase 11 relating to an additional review of design control and a review of a portion of RHR system design.

During subsequent hearings before the ASLB in September 1983, the scope of the independent assessment program was questioned.

In response to the ASLB Order of December 1983, the Applicant broadened the scope of the Cygna review. This expanded review was designated Phase III and Phase IV of the Cygna report. Phase III consists of pipe and pipe support review of the main steam and component cooling water system and review of quality assurance and corrective action measures. Phase IV is an independent design verification program of the component cooling water system, 4.2 ACTION ITEMS Cygna Energy Services has forwarded questions relating to seven generic issues which when answered will resolve all remaining outstanding issues. These generic issues are identified in Table 4-1, Sheets 1-8.

The generic issues will be addressed in action plans of the Comanche Peak Response Team (CPRT). Other CPRT activities are covered in Section 2.0.

4.3 CONCLUSION

TUGC0/CPRT will respond to each of these issues as to schedule and

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impact in a separate document.

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CPSES/ CAL TABLE 4-1 p()

INDEPENDENT ASSESSMENT PROGRAM (Sheet 1 of 8)

TABLE OF CONTENTS a

Generic Issue Sheet Pipe Stress 2

Pipe Supports 3

Cable Tray Supports 4

Conduit Supports 5

Mechanical Systems 6

Electrical 7

Design Control 8

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CPSES/ CAL TABLE 4-1 (Sheet 2) e PIPE STRESS GENERIC ISSUES

SUMMARY

DETAILED DESCRIPTION: Two major issues remain as open items:

1.

Mass participation 2.

Cunnulative effects of five piping analyses analyses observations

REFERENCE:

Cygna letter 84056.060 Attachment A dated March 29, 1985.

ACTION REQUIRED: TUGC0/CPRT to resolve the generic issue.

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CPSES/ CAL TABLE 4-1 (Sheet 3)

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PIPE SUPPORTS GENERIC ISSUES

SUMMARY

DETAILED DESCRIPTION:

Two major issues remain as open items:

1.

Design loads and displacements.

2.

Design of support components.

REFERENCE:

Cygna letter 84056.060 Attachment B, dated March 29, 1985.

ACTION REQUIRED:

TUGC0/CPRT to resolve the generic issue.

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CPSES/ CAL TABLE 4-1 (Sheet 4)

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CABLE TRAY SUPPORTS

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GENERIC ISSUES

SUMMARY

DETAILED DESCRIPTION:

Five major issues remain as open items:

1.

Design loadings.

2.

Response spectra analysis.

3.

Generic studies 4.

Systems concept for design 5.

Component design

REFERENCE:

Cygna letter 84056.060 Attachment C, dated March 29, 1985.

ACTION REQUIRED:

1.

Cygna complete documentation of support reviews and investigation of design specified support spacing.

2.

TUGC0/CPRT to resolve the generic issue.

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CPSES/ CAL TABLE 4-1 (Sheet 5)

O CONDUIT SUPPORTS GENERIC ISSUES

SUMMARY

DETAILED DESCRIPTION: Three major issues remain as open items:

1.

Design loadings 2.

Systems concept for design 3.

Component design

REFERENCE:

Cygna letter 84056.060 Attachment D, dated March 29, 1985.

ACTION REQUIRED:

1.

Cygna complete documentation of support reviews and specific investigations.

2.

TUGC0/CPRT to resolve the generic issue.

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CPSES/ CAL TABLE 4-1 (Shcet 6)

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MECHANICAL SYSTEMS GENERIC ISSUES

SUMMARY

DETAILED DESCRIPTION:

Three major issues remain as open items:

1.

Single failure criteria 2.

Changes in design parameters 3.

Control of Appendix R modifications

REFERENCE:

Cygna letter 84056.060 Attachment E, dated March 29, 1985.

ACTION REQUIRED: TUGC0/CPRT to resolve the generic issue.

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CPSES/ CAL TABLE 4-1 (Sheet 7) gs

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ELECTRICAL GENERIC ISSUES

SUMMARY

DETAILED DESCRIPTION:

One item of potential significance remains open:

1.

Pressure-Temperature ratings of Component Cooling Water (CCW) system instruments.

REFERENCE:

Cygna letter 84056.060 Attachment F, dated March 29, 1985.

ACTION REQUIRED: TUGC0/CPRT to resolve the generic issue.

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CPSES/ CAL TABLE 4-1 (Sheet 8) me)

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DESIGN CONTROL GENERIC ISSUES

SUMMARY

DETAILED DESCRIPTION: Two items remain open:

1.

Corrective action 2.

Document control

REFERENCE:

Cygna letter 84056.060 Attachment G, dated March 29, 1985.

ACTION REQUIRED:

1) TUGC0/CPRT to resolve the generic issue.

2) Cygna to complete cumulative effects evaluation to close the generic issue.

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CPSES/ CAL 5.0 SAFETY EVALUATION REPORT

5.1 INTRODUCTION

This chapter addresses the licensing issues that have been identified by NRR in the CPSES Safety Evaluation Report (SER), Supplemental Safety Evaluation Reports (SSER), or NRR correspondence and have not been closed in a later SSER or letter from NRR. These issues fall into four basic groups. These groups are:

1.

Outstanding Issues 2.

Confirmatory Issues 3.

License Conditions 4.

Open Correspondence The SSER items that are applicable to the NRC Technical Review Team and the Independent Assessment Program are addressed in Chapters 2 and 4, respectively.

5.2 ACTION ITEMS 5.2.1 OUTSTANDING ISSUES As a result of the staff review of the safety aspects of the CPSES application, a number of items remain outstanding from the standpoint that CPSES and the staff have not reached final positions on these items. The cutstanding issues are listed in Table 5-1.

5.2.2 CONFIRMATORY ISSUES As a result of the staff review of the safety aspects of the CPSES application, a number of items have Daen resolved, but the item will not be closed until the NRC staff confirms that agreed upon actions are completed. The confirmatory issues are listed in Table 5-2.

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CPSES/ CAL 5.2.3 LICENSE CONDITIONS AV Items exist for which a condition may be added to the operating license to provide additional assurance to the NRC staff that these requirements are met during plant operation. Preliminary license conditions are listed in Table 5-3.

5.2.4 OPEN CORRESPONDENCE In. addition to the issues and concerns identified in the SER and SSERs, the NRC staff requests additional information in various areas to assist the staff in its evaluation of CPSES. These requests may relate to previously defined' issues or, if unresolved, may become an new open issue or license condition in a future SSER.

The status of all outstanding requests for additional information (or any other requests from the NRC staff relating to the safety review of CPSES) are tabulated and discussed in Table 5-4.

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5.3 CONCLUSION

S CPSES recognizes the need to resolve all the SER items identified in this chapter. The TUGC0 Licensing organization is interfacing with the appropriate CPSES organizations and.:ith the NRC staff.

Input to the staff is provided as expeditiously as possible to ensure that these items will not affect any phase of CPSES Unit 1 operation.

All of the Outstanding Issues for which TUGC0 action has been defined, are scheduled to De completed in the near term (by 6/15/85) except for one (see Table 5-1, Sheet 7) which the NRC staff has agreed need not be completed prior to exceeding 5% power. As described in Table 5-1, CPSES Unit 1 can operate safely through 5% power while these issues are being resolved and, except for three items, can operate safely for its first cycle.

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CPSES/ CAL The only Confirmatory Issues with action required by TUGC0 is scheduled to be completed by 5/20/85. The impact discussions on all the remaining

-V-Confirmatory Items indicate that CPSES Unit 1 can safely operate for the first cycle while these items are being closed.

None of the License Conditions requires TUGC0 action prior to fuel load except for the identification of Preoperational Tests that require deferral (see Chapter 8).

Some of the License Conditions require revision by the NRC staff prior to' license issuance.

All items are sufficiently complete that adequate assurance of the safe operation of CPSES Unit 1 through the first cycle is provided.

The Open Correspondence items in Table 5-4 were addressed in Tables 5-1 or 5-2 and therefore have no additional impact.

In summary, none of the items in this Chapter will impact the ability of CPSES Unit 1 to operate through 5% power and very few, if any, will impact the ability of CPSES Unit I to safely operate through its first cycle. All defined TUGC0 actions are scheduled to be completed by 7/1/85 and most are scheduled to oe completed much sooner.

O-5-3

CPSES/ CAL TABLE 5-1 O

SER Du1 STANDING issues (Sheet 1 of 11)

ITEM INDEX Title Sheet l

Inspection Program for Pumps and Valves 2

Remote Safe Shutdown 3

Heavy Loads 4

Appendix R S

Security Plan 6

Control Room Design Review 7

Steam Generator Tube Rupture 8

Containment Sump Performance 9

Safety Parameter Display System 10 Integrated Leak Rate Test 11 G

J

CPSES/ CAL TABLE 5-1 (Sheet 2)

INSPECTION PROGRAM FOP. PUMPS AND VALVES DETAILED DESCRIPTION: Preservice and inservice inspections and testing pr_ogram for pumps and valves.

SER/SSER

REFERENCE:

SSER #6, Section 1.7, Item (7). FSAR Sections 3.9.2.1 and 3.9.6.

ACTION REQUIRED:

NRC staf f review of the CPSIS program followeo oy comments or closure.

STATUS AND SCHEDULE: The CPSES program was suomitted oy TXX-4062 of 10/12/83.

IMPACT: This item is sufficiently complete SJch that there should be no impact on any phcse of CPSES Unit 1 operation.

'O l

O

(

CPSES/ CAL TABLE 5-1 i

~

(Sheet 3)

O REMOTE SAFE SHUTDOWN DETAILED DESCRIPTION:

Remote (alternative) safe shutdown capability - installation of cold leg temperature Tc and source range neutron meter at the hot shutdown panel.

SER/SSER

REFERENCE:

SSER #6, Section 1.7, Item (19). FSAR Section 7.4.2.

ACTION REQUIRED: The NRC staff must review and accept the TUGC0 commitment to close this issue.

STATUS AND SCHEDULE: The TUGC0 commitment to install this backfit was suomitted by TXX-4242 of 7/27/84.

IMPACT: There is no impact on the safe operation of CPSES Unit I up to 5% power while this backfit is being installed.

j O

i O

CPSES/ CAL TABLE 5-1

O L

(Sheet 4)

HEAVY LOADS DETAILED DESCRIPTION:

Handling of heavy loads in conformance with the guidelines of NUREG-0612.

SER/SSER

REFERENCE:

SSER #6, Section 1.7, Item (23). FSAR Section 9.1.4.

ACTION REQUIRED: NRC staff review of the CPSES response to NRR letter of 9/21/84 followed by comments or closure.

STATUS AND SCHEDULE: The CPSES response to NRR letter of 9/21/84 was submitted by TXX-4395 of 1/22/85.

IMPACT: This item is sufficiently complete such that there should be no impact on any phase of CPSES Unit 1 operation.

~O O

CPSES/ CAL j

TABLE 5-1

. q-(Sheet 5) is APPENDIX R DETAILED DESCRIPTION: Fire protection program - conformance with the requirements of 10 CFR 50, Appendix R.

SER/SSER

REFERENCE:

SSER #6, Section 1.7, Item (24). FSAR Sections 8.4.6, 9.5.1 and 9.5.3.

ACTION REQUIRED: Respond to ASB questions 010.32 and 010.33 as provided by NRR letter of 3/8/85 and perform a breaker / fuse coordination study.

NRR review and accept the CPSES fire protection program.

STATUS AND SCHEDULE: Respond to questions by 4/30/85 and complete breaker fuse study Dy 6/15/85.

IMPACT: Fission product inventory prior to exceeding 5% power is not significant due to the low power history. CPSES can be safety operated through 5% power while the study is being completed.

(See also Table 5-4, Sheet 3 Table 6-1, Sheets 2, 4, 16, 20,- 24, 25, 26, 27, and 28; Table 7-1, Sheets 22, 24, 25, 26 and 27; and Table 8-1, Sheets 5 and 8)

O

. _. ~ _ _ _

i CPSES/ CAL TABLE 5-1

. O (Sheet 6)

SECURITY PLAN DETAILED DESCRIPTION:

Security plan and security training and qualification plan.

SER/SSER REFEREN_CE_: SSER #6, Section 1.7, Item (28). FSAR Section

- 13.6.

4 ACTION REQUIRED:

NRC to schedule and conduct a site confirmatory audit.

STATUS AND SCHEDULE: The CPSES security program was resolved in SSER 96.

i IMPACT: Pending the NRC site audit, this item is sufficiently complete such that there should be no impact on any phase of CPSES Unit i operation.

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CPSES/ CAL TABLE 5-1 O

(Sheet 7)

COI T L ROOM DESIGN REVIEW DETAILED DESCRIPTION:

Control room design must be reviewed to ensure a design that enhances the operators' ability to operate the unit.

SER/SSER

REFERENCE:

SSER #6, Section 1.7, Item (30)(e). FSAR Section I.D.1 ACTION REQUIRED: TUGC0 needs to install the control room carpet and rerun the environmental surveys. TUGC0 also needs to resolve certain specific Human Engineering Discrepan::ies (HED's). A report must be submitted to the NRC staff on the results of these activities. The final Detailed Control Room Design Review (DCRDR) must be submitted.

The NRC staff needs to approve the TUGC0 schedule for the DCRDR Report.

STATUS AND SCHEDULE _:

Most HED's are complete. The remaining HED's are being integrated into the availability of the Control Room. TUGC0 has proposed that the final DCRDR Report be submitted prior to startup for the second operating cycle (see TXX-4328 of 10/5/84).

IMPACT: The NRC staff has allowed in SSER #6 that CPSES may operate up to 5% power while the environmental surveys are rerun and the specified HED's are resolved.

Completion of the DCRDR will not affect safe operation of CPSES Unit 1.

O

.. - _ - _ =.

CPSES/ CAL TABLE 5-1

,(

(Sheet 8)

STEAM GENERATOR TUBE RUPTURE DETAILED DESCRIPTION: Steam generator tube rupture - isolation of steam generator within 30 minutes.

4 SER/SSER

REFERENCE:

SSER #6, Section 1.7, Item (31). FSAR Section 15.6.

ACTION REQUIRED:

NRC issue license condition.

l STATUS AND SCHEDULE: NRR letter of 11/27/84 defers the resolution of l

this item pending the results of the Westinghouse Owners Group analysis.

)

IMPACT: This item is sufficiently complete such that CPSES can operate safely until the issue is completely resolved.

1 f

l 4

O

CPSES/ CAL TABLE S-1 (v)

(Sheet 9)

CONTAINMENT SUMP PERFORMANCE DETAILED DESCRIPTION:

Containment sump performance.

SER/SSER

REFERENCE:

SSER #6, Section 1.7, Item (34) and SSER #9. FSAR Section 6.2.

ACTION REQUIRED:

CPSES provide FSAR update.

STATUS AND SCHEDULE: An FSAR update is scheduled for 4/30/85.

IMPACT: This item is sufficiently complete such that there should De no impact on any phase of operation for CPSES Unit 1.

O

CPSES/ CAL TABLE 5-1

{

(Sheet 10)

SAFETY PARAMETER DISPLAY SYSTEM DETAILED DESCRIPTION:

Safety parameter display system (SPDS) design and parameter analysis.

SER/SSER

REFERENCE:

SSER #6, Section 1.7, Item (35).

FSAR Section I.D.2.

ACTION REQUIRED:

TUGC0 will respond to NRR letter of 12/5/84. The NRC staff can us'e Ihis response to close this issue.

~

STATUS AND SCHEDULE: TUGC0 is in the process of developing the required response which is scheduled to be submitted Dy 4/30/85.

IMPACT: CPSES cai be safely operated at full power while this item is being resolved.

(See also Table 6-1, Sheet 17)

O O

CPSES/ CAL TABLE 5-1 (Sheet 11)

O INTEGRATED LEAK RATE TEST DETAILED DESCRIPTION:

Integrated leak rate test (ILRT) methodology.

SER/SSER

REFERENCE:

SSER #6, Section 1.7, Item (36).

FSAR Section 6.2.5.

ACTION REQUIRED:

NRC review of the CPSES response to ILRT question (issued by NRR letter of 8/27/84) followed by comments or closure.

STATUS AND SCHEDULE:

The CPSES response to the ILRT question was submitted by TXX-4386 of 12/21/84.

IMPACT: This item is sufficiently complete such that there should be no impact on any phase of CPSES Unit 1 operation.

O O

CPSES/ CAL TABLE 5-2 O

sea Coariaa^toav tsSuc5 (Sheet 1 of 7)

ITEM INDEX

i

' O O

CPSES/ CAL TABLE 5-4 O

(Sheet 23 PURGE AND VENT VALVE OPERABILITY DETAILED DESCRIPTION: NRC requested additional information and commitments concerning the operability of containment isolation valves for the ventilation lines that penetrate containment.

REFERENCE:

NRC letter of 11/9/84.

(See Table 5-2, Sheet 2)

O f

i 1

I iO 1

L

CPSES/ CAL TABLE 5-4 O

(Sheet 3)

SAFE AND ALTERNATE SHUTDOWN DETAILED DESCRIPTION: NRC requested additional information on Safe Shutdown and Alternate Shutdown.

REFERENCE:

NRC letter of 3/8/85.

ACTION REQUIRED: TUGC0 will develop and submit responses to these questions.

Both the question and responses will be documented in the FSAR.

STATUS AND SCHEDULE:

Engineering has the questions and is preparing the required technical input. The responses are expected to be submitted by 4/30/85.

IMPACT: No impact on the safe operation of CPSES Unit 1 has been identified based on these questions.

O (See also Table 5-1, Sheet 5, Table 6-1, Sheets 25 and 26 and Table 7-1, Sheet 27)

O

CPSES/ CAL TABLE S-4 (Sheet 4) l REQUIRED ACTIONS BASED ON GENERIC IMPLICATIONS 0F SALEM ATWS EVENT (GENERIC LETTER 83-28) i DETAILED DESCRIPTION:

NRC requested additional information concerning the C'PSES response to Generic Letter 83-28.

REFERENCE _: NRC letter of 4/12/85.

ACTION REQUIRED: TUGC0 will develop and suo. nit a response to these questions.

STATUS AND SCHEDULE: The response to the questions is scheduled to be suanitted Dy S/15/85.

IMPACT:

ho impact on the safe operation of CPSES Unit I has been identified based on these questions.

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O

CPSES/ CAL i

6.0 ENGINEERING AND CONSTRUCTION

6.1 INTRODUCTION

This chapter addresses action items associated with engineering and construction activities and Significant Deficiency Analysis Reports.

6.2 ACTION ITEMS TUGC0 uses a Master Data System to track open engineering and construction items. This list is updated on a weekly basis. The printouts from this system are used as a tool to schedule work, establish priorities and turn over systems to Operations. The entries in the system come from sources such as Non-conformance Reports, Design Deficiency Reports, Test Deficiency Reports and various design change dccuments. Section 6.2.1 below addresses the more significant items in the Master Data System while Section 6.2.2 addresses the resolution of the Master Data System in its entirety.

O 6.2.1 SIGNIFICANT ITEMS TUGC0 identified the significant engineering and construction items that are incomplete and are not addressed in another chapter using the following criteria:

Required to meet CPSES licensing requirements or commitments, Not a minor work item (a minor work item is an item which can be completed within about 30 days although not necessarily scheduled to be completed within the next 30 days),

A formal deferral has not Deen granted by NRR, and Deferral may require review Dy the NRC staff.

O 6-1

l CPSES/ CAL Q

TUGC0 submitted a tabulation of significant engineering and construction l

items in letter TXX-4389 of January 5, 1985 and updated that submittal with letter TXX-4399 of January 18, 1985. Table 6-1 updates and supercedes these previous sub:nittals.

6.2.2 MASTER DATA SYSTEM RESOLUTION All items on the Master Data System will be addressed by TUGC0 prior to the operation of CPSES Unit 1.

Each item will be screened.

Items that could potentially impact licensing requirements, licensing commitments, or the safe operation of CPSES Unit I will oe evaluated to assure that CPSES can safely and properly procede through fuel load, heatup, initial f,

criticality, 5% power and full power wnile each item is being completed.

This screening and evaluation process will be available for NRC review and inspection on site.

6.2.3 SIGNIFICANT DEFICIENCY ANALYSIS REPORTS O

Six open Significant Deficiency Analysis Reports (SDARs) are listed in Table 6-2.

6.3 CONCLUSION

S Each open engineering and construction item will be completed, resolved, or justified to allow the safe operation of CPSES Unit 1 or a formal deferral will be requested from the hRC staff.

Of the items in Table 6-1, the majority (20 out of 33) only involve TUGC0 completion of the work defined in the table. Four others are confirmatory in nature in that TUGC0 will complete the work and inform the NRC staff when tne work is done.

Similarly, two require TUGC0 completion of the work and a change to the technical specifications by NRR. Only seven require the submittal of new information for NRR review and acceptance.

O I

6-2 t

CPSES/ CAL None of these items would prevent fuel load for CPSES Unit 1.

Two items l

need to be completed prior to entering Mode 4 (heating up aDove 2000F).

The remaining items are either not required until at least 5% power or clearly have no impact on CPSES Unit 1 first cycle operation.

Of the six SDAR's in Table 6-2, four are resolved by action items already addressed in Table 6-1.

The three remaining SDAR's are l

l, scheduled to be completed within the next 30 days.

The engineering and construction items discussed in this chapter and the open SDAR's are not expected to have an adverse impact on the fuel load schedule for CPSES Unit 1.

n

. v 6-3

CPSES/ CAL TABLE 6-1 O

stoatetcaat eactaccatas aao coaSTauCTION 11E,5 (Sheet 1 of 34) t ITEM INDEX Title Sheet Appendix R Emergency Lighting 2

l Piping Analysis 3

l Appendix R Fire Detection Panel 4

Emergency Evacuation Alarm 5

Fuel Building Roll-Up Door 6

Sump Isolation Valves 7

Diesel Generator Excitation 8

Diesel Generators 9

MSIV Bypass Valves 10 Auxiliary and Safeguards Building Ventilation 11 EQ Containment Pressure Relief Valves 12 Hot Shutdown Panel Bolts 13 Containment Spray Valves 14 EQ NSSS Auxiliary Relay Ra.:k 15 Appendix R RHR Valve 16 SPD3 Isolators 17 EQ B0P Analog Control System 18 Electrical Separation 19 l

Appendix R Turbine Building 111 Roof Slab 20 HELB Superheat 21 l

U-Bolt Torques 22 EQ Incore Thermocouples 23 i

(

Appendix R Chiller Package 24 l

Appendix R FPPR Design Verification 25 Appendix R Breaker / Fuse Coordination 26 f

l Appendix R Portable Communication 27 l

Appendix R Radio Repeater Systems 28 Pipe Interference Due to Thermal Expansion 29 l

Turbine Driven Auxiliary Feedwater Pump 30 Damper Actuation Bracket 31 f

EQ Active Valves 32 t

ERF Computer I/O Cabinets 33 EQ Pressurizer Safety Valve PI 34 l

l I

i

CPSES/ CAL TABLE 6-1 (Sheet 2) 7 APPENDIX R EMERGENCY LIGHTING DETAILED DESCRIPTION: Add 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> battery packs for emergency lighting in UPS inverter room and adjacent corridor.

MASTER DATA SYSTEM

REFERENCE:

01DM-0445S ACTION REQUIRED: TUGC0 complete the design, installation and inspection of these new 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> battery packs and their associated supports and catling.

STATUS AND SCHEDULE:

This item is scheduled to be completed by 5/27/85.

IMPACT: Fission product inventory prior to 5% exceeding power is not significant due to the low power history.

Thus a fission product release due to a fire in this area is unlikely. CPSES Unit I can be safely operated up to 5% power while this modification is being O

co Pieted.

(See also Taole 5-1, Sheet 5 and Table 7-1, Sheet 24) i O

CPSES/ CAL TABLE 6-1 p>

(Sheet 3) t PIPING ANALYSIS DETAILED DESCRIPTION: The piping analysis was performed using estimated valve weights. The impact of the actual valve weights must be assessed and resolved.

MASTER DATA SYSTEM

REFERENCE:

9800-02585 ACTION REQUIRED: TUGC0 re-analyze piping systems as necessary to incorporate actual valve weights.

STATUS AND SCHEDULE: TUGC0 has determine the actual valve weights.

TUGC0 has analyzed several " worst case" problems and has determined that the CPSES piping design is still adequate.

TUGC0 will complete this item with the other piping analysis items being addressed by the CPRT action plans.

IMPACT:

This item, when taken alone, does not impact the licensing or 7_

'Q safe operation of CPSES Unit 1.

O

CPSES/ CAL TABLE 6-1 (Sheet 4)

APPENDIX R FIRE DETECTION PANEL DETAILED DESCRIPTION:

NFPA 72D requires that the fire detection panels (main and local) be verified to be operable for their intended use.

Factory Mutual (F.M.) has reviewed and approved the panels with one minor exception which is being resoluted. Also the panels must undergo an environmental testing for F.M. certification.

MASTER DATA SYSTEM

REFERENCE:

0613-0390S ACTION REQUIRED: No modifications are required in the field except for a recorder modification.

STATUS AND SCHEDULE _:

To oe completed by 3/31/86.

(environmental test)

IMPACT:

F.M. has found the panels to be operationally adequate with a minor exception concerning the recording of the time that the annunciator alarm is acknowledged. This does not affect the ability to detect and annunicate a fire condition.

Environmental testing will verify the ability of the panels to operate under some high unlikely adverse conditions, implementation of the defense-in-depth concepts has provided multiple layers of fire protection independent of the detection system.

CPSES Unit 1 can De safely operated through the first cycle while the environmental testing is being completed.

(See Table 5-1, Sheet 5, Table 7-1, Sheet 25 and Table 8-1, Sheet 5)

O

CPSES/ CAL TABLE 6-1 (Sheet 5)

EMERGENCY EVACUATION ALARM DETAILED DESCRIPTION: Upon testing, the emergency evacuation alarm failed to be clearly audible in areas of the plant where background noise exceeded 100 dB.

MASTER DATA SYSTEM

REFERENCE:

1201-0304S ACTICN REQUIRED: TUGC0 complete the design changes, install the modifications and retest the system.

STATUS AND SCHEDULE:

Appropriate solutions have oeen determined for each area and, where required, a visual alarm (a flashing light) will be installed. This item is scheduled to be completed by 7/15/85.

IMPACT _: The emergency evacuation alarm is used solely for evacuation of plant personnel to prevent possible injury from radiation exposure and therefore does not affect the health and safety of the public. Fission product inventory prior to exceeding 5% power is not significant due to O

the low power history. There is no impact on CPSES operations through at least 5% power while this item is being completed.

(See also Table 8-1, Sheet 12)

O

CPSES/ CAL TABLE 6-1 (Sheet 6)

FUEL BUILDING ROLL-UP 000R DETAILED DESCRIPTION:

1.

There is excessive air leakage through the roll-up door in the fuel building.

2.

With corridor doors open between buildings (for tornado venting) the building supply air trunk dampers are modulated erratically by the pressure controls.

MASTER DATA SYSTEM

REFERENCE:

2401-0242S 2401-02435 2401-02445 4201-0040S ACTION REQUIRED /

STATUS AND SCHEDULE:

1.

TUGC0 replace the existing roll-up door with a new low-leakage door. This item is scheduled to be completed oy 7/26/85.

2.

TUGC0 lock open the building modulating

]

supply dampers.

Building pressure will be controlled by supply and exhaust fan operation. This item is scheduled to be completed by 5/10/85.

When the modifications are complete, TUGC0 will balance the system and perform the differential pressure and flow tests.

(ECD 9/2/85).

IMP ACT_:

1.

No spent fuel will be stored in the Fuel Building, therefore operation through the first cycle is acceptable.

2.

Fission product inventory prior to exceeding 5% power is not significant.

Thus a fission product release due to a failure of the building modulating dampers is unlikely.

CPSES Unit I can be operated safely up to 5%

power while this modification is being completed.

(See also Table 8-1, Sheets 9 and 10)

O

CPSES/ CAL TABLE 6-1 (Sheet 7)

SUMP ISOLATION VALVES DETAILED DESCRIPTION: Sump Isolation Valves 8811A & B have motor operators that were environmentally qualified to an environment lower than required.

MASTER DATA SYSTEM

REFERENCE:

5801-04365 r

ACTION REQUIRED:

TUGC0 obtain and accept final documentation to show that existing operators are qualified for the correct postulated I

environment.

STATUS AND SCHEDULE:

Input must De received from Westinghouse for l

review and acceptance. A preliminary evaluation has shown that the existing operators are acceptable. This item is scheduled to be closed by 5/31/85.

l l

IMPACT: No impact is expected. The potential for an adverse environment and the need for operability for these valves is extremely

/~'

low prior to exceeding 5% power. The fact that the valves are

\\v) new/ unaged valves further mitigates any operational or safety concerns.

l l

1 l

l 0

CPSES/ CAL TABLE 6-1 (Sheet 8)

DIESEL GENERATOR EXCITATION DETAILED DESCRIPTION: Modifications were required to the maximum excitation limitors for the diesel generators.

MASTER DATA SYSTEM

REFERENCE:

2904-02135 2904-02085 ACTION REQUIRED: TUGC0 complete installation of the modification and retest. TUGC0 obtain new input from the vendor to update the equipment qualification package.

STATUS AND SCHEDULE:

The final modifications have been approved and are awaiting parts. The modification and qualification report are expected to be completed by 6/30/85.

IMPACT:

CPSES can be safely operated up to at least 5% power while these modifications are being reviewed and approved.

(See also Table 8-1, Sheet 14) i llO l

i

CPSES/ CAL TABLE 6-1 (Sheet 9)

DIESEL GENERATORS DETAILED DESCRIPTION:

The NRC staff has required that the maximum emergency load requirements for the Diesel Generators be limited to 5740 kW.

_ MASTER DATA SYSTEM

REFERENCE:

2904-0247S ACTION REQUIRED:

The NRC authorize startup testing at the new limit and revise the SER and Tech. Specs. TUGC0 retest at the new load rating.

STATUS AND SCHEDULE:

All the items that the NRC staff has requirt.d prior to fuel load with respect to the emergency diesel generators are listed under Conclusion in Section 9.5.9 of SSER #6. The 5740 kW limit is based on a limit of a 185 psig brake mean effective pressure (BMEP) which is considered safe with respect to stress on the piston skirts and crankshaft. The need for this limit is based on concerns regarding these stresses at higher BMEP loadings, and because of open items in the implementation of the Owners Group Program Plan. Testing cannot be completed until authorized by the NRC Staff. TUGC0 has formally requested that the load limit be changed.

IMPACT: The establishment of the operating restriction is partially the result of the incomplete status of implementation of the Owners Group O

ero9r et tae ti e or iss# #ce-cheeses i# the st tes or implementation of the Owners Group Program include the completion of all on-site Phase I activities, the issuance and review of the CPSES Phase 11 report on the Design Review / Quality Revalidation (DR/QR), and the submission of Texas Utilities' response to the DR/QR report to the NRC.

The Owners Group has concluded that the CPSES Unit I diesel generators are capable of reliably operating at full rated load, in addition, Texas Utilities has taken actions to enhance and verify the reliability of the train A and B engines. These include recommendations made by the Owners Group and the NRC Staff. A maintenance and surveillance program has also been developed and submitted to the NRC for approval.

Since the review in SSER #6 for CPSES, Shoreham completed a long term relianility test on the piston skirts and Catawba completed a long term reliability test on the crankshaft, inspections following these tests showed that the crankshaft and piston skirts had performed adequately.

As shown by this testing, it is reasonable to assume that the diesel generators will perform adequately and reliably up to its rated power loading of 7000 kW.

Based on the above, Texas Utilities believes that the CPSES Unit 1 diesel generators will provide a reliable standby source of onsite power in accordance with General Design Criteria 17 without the operating restrictions imposed by the Staff.

(See also Table 5-3, Sheet 11 and Table 8-1, Sheet 3).

CPSES/ CAL TABLE 6-1 (Sheet 10) p v

MAIN STEAM LINE ISOLATION VALVE BYfASS VALVES DETAILED DESCRIPTION: Main Steam Isolation Vahe (MSIV) Bypass Valve pneumatic-hydraulic actuators will be replaced by manual operators.

Administrative controls will be instituted to assure a locked closed position after the MSIVs have been opened.

MASTER DATA SYSTEM

REFERENCE:

3401-12995 ACTION REQUIRED: TUGC0 procure' operators and complete design change paperwork to replace automatic cperators with manual operators. TUGC0 install the new operators and (aa;1ge the administrative procedures to ensure that the manual valves and MSIVs are operated in an acceptable manner. TUGC0 submit the technical justification for this modification, FSAR changes and recommended Techhical Specification changes. NRC staff review and accept and update the Technical Specifications.

STATUS AND SCHEDULE:

This item is scheduled to be completed by 6/15/85.

O IMPACT: These valves are only used to warm the Main Steam line to equalize pressure prior to opening the MSIVs. A fission product release during this period due to a failure of MSIV bypass valves is unlikely.

CPSES Unit 1 can be operated safely through mode 4 while modifications are being completed.

(See also Table 8-1, Sheet 13) 1 0

1 CPSES/ CAL TABLE 6-1 (Sheet 11)

AUXILIARY AND SAFEGUARDS BUILDING VENTILATION DETAILED DESCRIPTION:

Design modifications (to resolve SDAR 84-27) are required to maintain environmental parameters in the Safeguards, Fuel and Auxiliary Buildings following a LOCA with loss of off-site power.

MASTER DATA SYSTEM

REFERENCE:

02AL-0244S 02AL-0247S 2401-0239S 3201-0393S 3201-03945 3201-03975 3601-01515 3601-0156S 3601-01585 3604-00455 4201-0039S 9800-02545 9800-02555 9800-02575 O

ACTION RE0ulRED: TUGC0 complete and instali several design modifications. These include:

Lighting circuit changes Air balance retest HVAC damper modifications FSAR update Equipment qualification documentation changes STATUS AND SCHEDULE: This item is scheduled to be completed by 10/1/85.

IMPACT:

The lack of significant amounts of fission product generated during low power testing indicates the acceptability of power operation up to 5% While this item is being resolved.

(See also Table 6-2, Sheet 4 and Table 8-1, Sheet 9 and 10).

O

CPSES/ CAL TABLE 6-1 (Sheet 12)

EQUIPMENT QUALIFICATION 18 INCH CONTAINMENT PRESSURE RELIEF VALVES DETAILED DESCRIPTION:

Containment isolation dependability (purge valve operability analysis for LOCA-related dynamic loads).

MASTER / DATA SYSTEM

REFERENCE:

4501-00625 4501-00675 (See Table 5-2, Sheet 2)

O O

CPSES/ CAL TABLE 6-1 (Sheet 13)

HOT SHUTDOWN PANELS BOLTS DETAILED DESCRIPTION: Some of the cabinet connection bolts joining small and large cabinets together are missing.

MASTER DATA SYSTEM

REFERENCE:

8903-8039S ACTION REQUIRED: TUGC0 obtain the justifications for the acceptability of the as-Duilt panel from the vendor. TUGC0 review and accept these justifications.

STATUS AND SCHEDULE: Justification analysis has been produced.

Comments must be resolved. The expected completion date is 4/30/85.

IMPACT: No impact is expected for this item. The outstanding comments on the analysis are not expected to change the outcome.

O

CPSES/ CAL TABLE 6-1 s

(Sheet 14) 1

(_)

v

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CONTAINMENT' SPRAY VALVES e ' '.

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DETAILED DESCRIPTION:

Containment spray valves open too rapidly. This could cause the pumps to run-out.

t MASTER DATA SYSTEM

REFERENCE:

4802-07895 j'

ACTION REQUIRED: TUGC0 complete the design work to modify the valves and to change the control circuit to open the. outlet valves more slowly and to provide for coordinated closure of' the minimum flow valves.

TUGC0 provide an FSAR change to describe this< modification. TUGC0 procure the required hardware and then install, inspect and test the modification.

1 i

STATUS AND SCHEDULE: The design change package is under development.

This item is scheduled to be completed by 7/31/85.

t',

3 -;

' IMPACT: CPSES can safely load fuel and proceed through all activities

('.

up to heatup (mode 4), while this modification is being completed.

(See also Table 6-2, Sheet 5 and TaDie 8-1, Sheet 15) 1 I

,i i

I s

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CPSES/ CAL TABLE 6-1 (Sheet 15) fmO EQUIPMENT QUALIFICATION NSSS AUXILIARY RELAY RACK WIRING CHANGES DETAILED DESCRIPTION:

In order to properly establish the seismic qualification of the NSSS Auxiliary Relay Rack, the wiring must be slightly rerouted within the rack to provide the best possible separation.

MASTER DATA SYSTEM

REFERENCE:

5201-10395 ACTION REQUIRED:

TUGC0 retest.the circuits affected by the wiring changes. TUGC0 obtain the necessary information from Westinghouse to complete and accept the qualification of this rack.

STATUS AND SCHEDULE:

A JIO was submitted on the NSSS Auxiliary Relay Racks by TXX-4304 of Septemoer 20, 1984.

In an NRR letter of December 4,1984, the NRC staff provided a draf t license condition that required that the wiring changes be completed prior to fuel load. The changes and testing are expected to be completed by 5/31/85.

IMPACT: Separation is provided within the NSSS Auxiliary Relay Racks without the modifications. The modifications were made to provide the greatest degree of separation possible within the as-Duilt racks.

None of the circuitry within this rack is involved in protective functions and none of the equipment served provides a safety related function.

However, certain circuits within the rack were routed and treated as Class 1E. Therefore, the separation within the rack has been maximized to protect against the remote possibility that a fault would occur in a non-safety circuit within the rack of such magnitude and of such a nature that one of the train designated circuits within the rack would be affected in a manner that the train designated circuit would in turn jeopardize a safety related component or power supply.

Considering these facts as well as the fact that there is no significant buildup of fission products in the core below 5% power, it can be concluded that CPSES can safely load fuel and operate up to 5% power without completion of the proposed wiring changes.

i

CPSES/ CAL TABLE 6-1 (Sheet 16) 0-APPENDIX R RHR VALVE DETAILED DESCRIPTION:

Fire could cause a loss of instrument air to the RHR heat exchanger control valves causing them to fail in a position which results in a plant cooldown rate in excess of technical specification limits.

MASTER DATA SYSTEM

REFERENCE:

5801-0432S ACTION REQUIRED: TUGC0 prepare a design modification to allow the use of portable air compressors to assure the operability of these valves.

TUGC0 implement, inspect and test the design change and update the appropriate operational procedures.

STATUS AND SCHEDULE:

The electrical system is scheduled to De modified by 5/30/85 to allow usage of a portable air compressor powered from either train "A" or "B" to supply operating air to these valves.

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IMPACT: Fission product inventory prior to exceeding 5% power is not significant due to the low power history. Thus a fission product

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release due to a fire in this area is unlikely.

CPSES Unit 1 can be safely operated while this modification is being completed.

(See also Table 5-1, Sheet 5)

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I CPSES/ CAL TABLE 6-1 (Sheet 17)

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SPDS ISOLATORS DETAILED DESCRIPTION: The NRC staff has requested specific information on the Safety Parameter Display System (SPDS) isolators.

MASTER DATA SYSTEM

REFERENCE:

7401-0035S 4

ACTION REQUIRED: TUGC0 install fuses as an interim solution. TUGC0 complete the requested analysis prior to the end of the first operating cycle. NRR review and accept the TUGC0 interim solution.

STATUS AND SCHEDULE:

TXX-4384 of 1/7/85 describes the installation of fuses as an interim solution and justifies the safe operation of CPSES Unit 1 through the first cycle. These fuses have been installed. The final evaluation of the system is scheduled to be suomitted prior to the second operating cycle for Unit 1.

J IMPACT:

None during first operating cycle for Unit 1.

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(See also Table 5-1, Sheet 10)

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m CPSES/ CAL TABLE 6-1 (Sheet 18)

,O EQUIPMENT QUALIFICATION B0P ANALOG CONTROL SYSTEM DETAILED DESCRIPTION: Some minor seismic qualification problems with the BOP Analog Control System need to be resolved. Several minor hardware modifications must be made (card replacement).

MASTER DATA SYSTEM

REFERENCE:

8801-01035 ACTION REQUIRED: TUGC0 complete the required card replacements and retest the affected circuits. TUGC0 obtain the information from Westinghouse to complete and accept this qualification package.

STATUS AND SCHEDULE:

A JIO (MS 611B) was submitted by TXX-4208 of June 29, 1984.

The JIO gave an estimated completion date of 12/31/84 but concluded that CPSES could safely operate until tnis package has been completed. All card replacements have been completed. The new cards are being calibrated and the circuits affected by the hardware replacement are Deing rechecked. This item is scheduled to be completed by 5/15/85.

IMPACT: The NRC staff has approved deferral of completion of this qualification package until 5% power (see NRR letter of December 4, 1984).

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CPSES/ CAL TABLE 6-1 (Sheet 19) pv ELECTRICAL SEPARATION DETAILED DESCRIPTION: When cable wrap is used as a separation barrier, the minimum separation distance recommended by R. G. 1.75 between cable and barrier could not always be maintained.

MASTER DATA SYSTEM

REFERENCE:

8900-0064S 8900-0066B ACTION REQUIRED:

TUGC0 perform an evaluation to justify the existing design or to make modifications. TUGC0 submit the results of this evaluation and the justification to NRR. NRR review and accept this aspect of the CPSES design.

STATUS AND SCHEDULE:

This item was discussed with the NRC staff on 8/23/84 and feedoack was sent to engineering. This item is scheduled to be completed by 8/16/85.

IMPACT:

The fire wrap is 1.5 inches of fire rated B&B HEMYC blanket.

O The separation distance is less than the recommended values in areas d

where it was physically not possible to separate the cables any further such as at wall or floor penetrations. Even though one cable touches the barrier of a second cable, the two cables are separated by 1.5 i

inches (the width of the barrier).

Based on these facts, interim acceptance of this separation is reasonable for up to 5% power.

CPSES Unit I can De safely operated up to 5% power while this analysis is being completed.

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CPSES/ CAL TABLE 6-1 (Sheet 20)

O APPENDIX R TURBINE BUILDING FIRE ZONE 111 CEILING SLAB AT ELEVATION 821-8 DETAILED DESCRIPTION: HVAC ducts penetrating the E&C building through three hour fire barriers contain dampers not rated as three hour barriers. Credit has been given for the integrity of the duct. This integrity is compromised if the ceiling slab collapses due to a fire in the area of the deck structural supports. This ceiling slab was intended to provide a three hour barrier but does not meet all the requirements for a three hour Darrier.

MASTER DATA SYSTEM

REFERENCE:

9800-0256S ACTION REQUIRED: NRR review and accept the deviation requests provided by TUGCO.

(See TXX-4422 dated 2/19/85).

STATUS AND SCHEDULE: The supports exposed to a turbine building fire have been provided with 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> protection. A deviation has been requested for the other supports and ceiling slab itself. This item

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will be closed when the NRC staff reviews and accepts the deviation requests.

IMPACT: CPSES Unit 1 can be safely operated while these deviation requests are being reviewed.

(See Table 5-1, Sheet 5)

CPSES/ CAL TABLE 6-1 fl (Sheet 21) v HELB SUPERHEAT DETAILED DESCRIPTION: An HELB in a Main Steamline (SDAR 84-12) outside containment could result in temperatures that exceed current qualification values in the room where the break occurs.

MASTER DATA SYSTEM

REFERENCE:

9800-01125 ACTION REQUIRED: TUGC0 perform a plant specific analysis of the event and submit to NRR. NRR review and accept this analysis.

STATUS AND SCHEDULE:

A full status of this issue was submitted to the NRC on September 28, 1984, in TXX-4320. This status showed that, based on typical data, the accident environment is such that all electrical equipment that is required to operate will not exceed its current qualification limits. A final analysis cannot be performed until final CPSES data on the break is received from Westinghouse.

1 In an NRR letter dated December 21, 1984, additional information was requested by the NRC staff. A response was provided oy TXX-4413 of m(j 2/14/85.

This item is scheduled to be completed by 7/31/85.

IMPACT: The TUGC0 submittals contained evidence that the CPSES design will adequately mitigate the HELB and allow for safe shutdown. This evidence is adequate to justify the safe operation of CPSES Unit 1 operation while the final analysis is being completed.

(See also Taole 6-2, Sheet 3)

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CPSES/ CAL TABLE 6-1 l

(Sheet 22)

O U-BOLT TORQUES DETAILED DESCRIPTION:

New torque values have been determined and must be verified for certain pipe supports that use U-bolts.

MASTER DATA SYSTEM

REFERENCE:

9800-01785 I

ACTION REQUIRED: TUGC0 complete the list of U-bolts to be torqued and the new torque values. TUGC0 complete the re-torquing requirement.

STATUS AND SCHEDULE:

A construction schedule has not been finalized to complete this item.

i IMPACT: Failure to torque the U-Dolts to the specified torque values prior to fuel load would not affect plant safety.

CPSES can safely load fuel and operate up to 5% power while this item is being completed.

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CPSES/ CAL TABLE 6-1 m

(Sheet 23)

V EQUIPMENT QUALIFICATION INCORE THERMOCOUPLES, CONNECTORS, ADAPT 0RS AND REFERENCE JUNCTION B0X DETAILED DESCRIPTION: The environmental qualification packages (ESE-43/44) for this equipment are not complete.

MASTER DATA SYSTEM

REFERENCE:

9800-01815 9800-0252S ACTION REQUIRED: TUGC0 complete, inspect and test the modifications required for this system. TUGC0 obtain the required input from Westinghouse to complete and accept these qualification packages. TUGC0 notify NRR when the qualification packages are complete.

STATUS AND SCHEDULE:

A JIO was submitted by TXX-4209 of June 29, 1984.

The JIO gave an estimated completion date of 2/28/85 and concluded that CPSES Unit 1 could be safely operated until this qualification program is completed. The NRC staff has indicated that deferral will be allowed until November 1985 as allowed by 10 CFR 50.49. Qualification is O

scheduled to be completed by 9/30/85. The hardware modifications are scheduled to be completed by 5/3/85.

IMPACT: This deferral should extend until November 1985. The JIO is correct except that some hardware is being replaced. This hardware will De replaced prior to exceeding 5% power.

(See also Table 5-3, Sheet 10) 1 O

CPSES/ CAL TABLE 6-1 f 's (Sheet 24) e V

APPENDIX R CHILLER PACKAGE DETAILED DESCRIPTION:

A fire in the cable spreading room could cause I

the loss of the Diesel Generator Sequencer. A loss of the sequencer could prevent operation of the safety related chiller package, i

MASTER DATA SYSTEM

REFERENCE:

3101-0248Z i

ACTION REQUIRED: TUG ^0 approve, implement and test a new design.

i STATUS AND SCHEDULE: Tnese changes primarily involve control logic changes. The design change has been approved. The estimated completion i

date is 5/15/85.

IMPACT: Fission product inventory prior to 5% power is ne.tigiole due to the low power nistory. Thus a fission product release due to fire in

+

this area is unlikely.

CPSES Unit 1 can ne safely operated up to 5%

power while this modification is being completed.

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(See also Table 5-1, Sheet 5) d 4

CPSES/ CAL TABLE 6-1 N

(Sheet 25)

(d APPENDIX R FPPR DESIGN VERIFICATION DETAILED DESCRIPTION: Fire Protection Program Review (FPPR) design verification includes review of 20 foot separation, 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> barriers, suppression and detection commitments. Follow-up work, if any, may include:

1.

deviation submittal 2.

update of FHA 3.

additional physical work (thermolag, seals, sprinklers, etc.)

MASTER DATA SYSTEM

REFERENCE:

9800-02045 9800-02175 9800-0228S ACTION REQUIRED: TUGC0 complete the required reviews, determine what additional action is required and develop a plan to resolve any new items. TUGC0 keep NRR informed about the status of this item. TUGC0 update the Fire Hazards analysis.

O STATUS AND SCHEDULE: The design verification is being expedited and is expected to be complete by 5/1/85. Schedules for any resulting work will be supplied after completion of verification.

IMPACT: Fission product inventory prior to exceeding 5% power is not significant due to the low power history. A fission product release during this period is unlikely. CPSES Unit 1 can be safely operated up to 5% while the verification is being completed. Follow-up work resulting from the verification, if any, will be evaluated and appropriate justification provided at that time.

(See also Table 5-1, Sheet 5, Table 5-4, Sheet 3 and Table 7-1, Sheet 27) l

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CPSES/ CAL l

TABLE 6-1 Os (Sheet 26)

APPENDIX R BREAKER / FUSE COORDINATION DETAILED DESCRIPTION:

In a request for additional information, the ASB of NRR has requested confirmation of proper breaker / fuse coordination for associated circuits.

MASTER DATA SYSTEM

REFERENCE:

9800-02095 ACTION REQUIRED: TUGC0 complete this study and notify NRR of the results. NRR review and accept to close issue.

STATUS AND SCHEDULE: A partial Dreaker/ fuse coordination audit was performed as part of the fire protection review for CPSES. This aspect of the CPSES design was also inspected by the NRC staff and their consultants during the Fire Protection Walk-down. The audit and inspection revealed areas that warrant additional investigation. The confirmation of CPSES breaker / fuse coordination will be completed by G/15/85.

IMPACT: A high confidence level exists in the CPSES design.

Breaker coordination has been considered in the past and was an element of the initial design of the CPSES electrical systems.

Based on the NRC staff questions, TUGC0 intends to examine this issue until complete and proper compliance is adequately confirmed. CPSES can oe safely operated while this issue is being resolved.

(See also Table 5-1, Sheet 5, Table 5-4, Sheet 3, and Table 7-1, Sheet 27).

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CPSES/ CAL TABLE 6-1 (Sheet 27) s APPENDIX R

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PORTABLE COMMUNICATION FOR OPERATORS AND FIRE BRIGADE DETAILED DESCRIPTION:

Lack of adequate portaDie communications restricts the ability of the fire brigade and operators to coordinate manual actions required during a fire. FCC licensing and a design to upgrade the current 40 watt operator channel to a 250 watt channel capable of communication inside plant ouildings is being implemented.

Also a new 250 watt channel is Deing installed for the use of the plant fire brigade.

MASTER DATA SYSTEM

REFERENCE:

9800-0219S ACTION REQUIRED: TUGC0 complete and approve the design change package.

TUGC0 procure and install the required additional hardware. TUGC0 obtain the new FCC license and retest the system.

STATUS AND SCHEDULE: To be completed by 7/30/85 contingent on the approval of the FCC license application.

pU IMPACT: The independent operator channel and fire brigade channel may not De available until after 5% power.

During the interim the backup security channel will be shared by the fire brigade and the operators in the event of a fire in which portable communications are required.

CPSES can be safely operated in this condition while this modification is Deing completed.

(See also Table 5-1, Sheet 5 and Table 7-1, Sheet 20)

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CPSES/ CAL TABLE 6-1 (Sheet 28)

O APPENDIX R RADIO REPEATER SYSTEMS DETAILED DESCRIPTION: Resolve portable communication dead spots in the radio repeater system due to plant as-built walkdown.

MASTER DATA SYSTEM

REFERENCE:

9800-02205 ACTION REQUIRED: TUGC0 complete and approve the design change package and procure the required hardware. TUGC0 retest the system and inform NRR of the results.

STATUS AND SCHEDULE: This item is scheduled to De completed by 6/1/85.

. IMPACT: Fission product inventory prior to exceeding 5% power is not significant due to the low power history. Thus, a fission product release during this period due to a fire is unlikely. CPSES Unit 1 can be safely operated up to 5% power while this modification is being completed.

(See also Table 5-1, Sheet 5 and Table 7-1, Sheet 20)

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CPSES/ CAL TABLE 6-1 (Sheet 29)

PIPE INTERFERENCE DUE TO THERMAL EXPANSION DETAILED DESCRIPTION:

Due to thermal expansion there are several areas where the pipe interference exists.

MASTER DATA SYSTEM

REFERENCE:

8902-80056 8903-79618 8924-0785B ACTION REQUIRED: TUGC0 complete the design changes or specific analyses necessary to resolve this item.

STATUS AND SCHEDULE: This item is scheduled to be completed by $/31/85.

IMPACT: No impact is expected from this item. A justification for each interaction to allow operation will ne prepared if necessary.

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CPSES/ CAL TABLE 6-1 dp (Sheet 30)

TURBINE DRIVEN AUXILIARY FEEDWATER PUMP DETAILED DESCRIPTION: Turbine Driven Auxiliary Feedwater Pump may not meet the discharge head acceptance criteria as described in the draft Technical Specifications.

MASTER DATA SYSTEM

REFERENCE:

9800-U116S ACTION REQUIRED: TUGC0 perform an evaluation to show that the discharge head developed by the pump is adequate.

TUGC0 submit an FSAR change and a recommended tech. spec. change to NRR.

NRR review and accept the evaluation and update the technical specifications.

STATUS AND SCHEDULE: This item is schedule to be resolved by 5/31/85.

IMPACT: The deviation of discharge head from acceptance criteria is only a few percentage points and should prove adequate with additional analysis.

Fission product inventory prior to exceeding 5% power is not significant due to the low power history. A fission product release is unlikely during this period. CPSES Unit 1 can be safely operated up to 5% power while the analysis is being completed and with a temporary exemption to the applicable technical specification.

CPSES/ CAL TABLE 6-1 (Sheet 31)

DAMPER ACTUATOR BRACKET DETAILED DESCRIPTION: Two HVAC damper actuator brackets need to be analyzed for seismic adequacy.

MASTER DATA SYSTEM

REFERENCE:

3601-0160S ACTION REQUIRED: TUGC0 obtain the analysis from the vendor. TUGC0 review and accept this analysis.

STATUS AND SCHEDULE: Evaluations are in progress. The expected completion date is 5/31/85.

IMPACT:

No impact is expected for this item. This bracket is similar to those which have Deen analyzed as adequate.

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CPSES/ CAL TABLE 6-1 (Sheet 32)

EQUIPMENT QUALIFICATION ACTIVE VALVES DETAILED DESCRIPTION:

In preparation of the CPSES Tech. Specs., several valves were identified as active that were previously classified as passive.

MASTER DATA SYSTEM

REFERENCE:

1101-0799S 1

ACTION REQUIRED: TUGC0 obtain the required information necessary to document the operability of these valves.

STATUS AND SCHEDULE: This item is scheduled to be completed by 5/17/85, Dut depends upon vendor input.

IMPACT: The seismic qualification of these valves and the installation of any additional stiffeners will be accomplished prior to exceeding 5%

power.

Based on the conservative seismic design at CPSES, the low probability of an earthquake between fuel load and 5% power, the lack of O

significant fission product Duildup prior to 5% power and the high confidence that exists for these valves, it can be concluded that CPSES Unit 1 can safely load fuel and operate up to 5% power while the seismic documentation is finalized and the installation of the additional stiffeners is completed.

CPSES/ CAL TABLE 6-1 (Sheet 33)

ERF COMPUTER I/O CABINETS DETAILED DESCRIPTION: Some terminal block points on the ERF Computer i

I/O Cabinets were found cracked (SDAR 85-06).

MASTER DATA SYSTEM

REFERENCE:

7801-00975 7801-00985 7801-01005 7801-01015 ACTION REQUIRED: TUGC0 evaluate the problem further to determine which terminal olocks must be replaced, which wiring must be changed and what additional inspections and tests are required.

STATUS AND SCHEDULE: Work to be completed oy 5/1/85.

IMPACT: All systems have been tested and work properly.

CPSES Unit 1 can startup and operate safely while this item is being corrected.

(See also Table 8-1, Sheet 4)

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CPSES/ CAL TABLE 6-1 (Sheet 34) 7._

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EQUIPMENT QUALIFICATION PRESSURIZER SAFETY VALVE POSITION INDICATION DETAILEO DESCRIPTION: The environmental qualification (HE-7) for position detection devices (Unit 1) for the Pressurizer. Safety Valves is not complete.

MASTER DATA SYSTEM

REFERENCE:

5501-0866S ACTION REQUIRED:

TUGC0 obtain the required input from Westinghouse to complete and accept this qualification package. TUGC0 to notify NRR when the qualification package is complete.

STATUS AND SCHEDULE: A JIO was submitted by TXX-4209 of June 29, 1984.

The JIO gave an estimated completion date of 2/28/85 and concluded that CPSES Unit 1 can be safely operated until this qualification package is completed. The NRC staff has indicated that deferral until November 1985 will be allowed as provided by 10CFR50.49. The qualification is scheduled to be completed by 9/30/85.

IMPACT: The failure of these position switches will not affect the integrity of any class 1E circuits or safety related systems. The qualification and operability of these switches is a backfit required by TMI Action Plan Item II.D.3 and Regulatory Guide 1.97, Rev. 2.

Because of the qualification problems experienced, it is reasonable to extend the deadline for this backfit to November 1985.

CPSES can be safely operated until Novemoer 1985 while this backfit is Deing Completed.

(See also Table 5-3, Sheet 10)

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CPSES/ CAL TABLE 6-2 I"3 SIGNIFICANT DEFICIENCY ANALYSIS REPORTS i

(Sheet 1 of 7)

ITEM INDEX Title Sheet

)

Thermal Expansion of Fire Dampers (84-08) 2 Environmental Qualification for High Energy Line Breaks (84-12) 3 Ventilation Exhaust Dampers (84-27) 4 s

i Containment Spray Header Valves (85-04) 5 Diesel Generator Air Filter Bowl (85-05) 6 l

Control Board Modeling (85-10) 7 1

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CPSES/ CAL TABLE 6-2 i, -)

(Sheet 2)

THERMAL EXPANSION OF FIRE DAMPERS DETAILED DESCRIPTION:

Installation of stw fire! l.1:npers could cause bindirig~ before actu'a' tion.

REFERENCE:

SDAR 84-08 ACTION REQUIRE 0:

Repair, replace or modify fire protection system to maintain appropriate fire barriers.

Notify the NRC staff that the item is resolved.

STATUS AND SCHEDULE:

All needed modifications have been identified and completed.

IMPACT: This item does not affect operations at CPSES Unit 1 prior to exceeding 5% power.

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i CPSES/ CAL TABLE 6-2

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(Sheet 3)

ENVIRONMENTAL QUALIFICATION FOR HIGH ENERGY LINE BREAKS 1

]

DETAILED DESCRIPTION: Equipment located in the Main Steam Valve Room may be subjected to higher temperatures resulting from superheated steam following blowdown of a steam generator resulting from a Main Steam Line break in this area.

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REFERENCE:

SDAR 84-12 l

(See Table 6-1, Sheet 21) i 4

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CPSES/ CAL TABLE 6-2

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VENTILATION EXHAUST DAMPERS DETAILED DESCRIPTION:

Some ventilation control dampers in safety area boundaries will fail closed on loss of electrical power and may cause excessive ambient temperatures in those areas.

REFEREhCE:

SDAR 84-27 (See Table 6-1, Sheet 11)

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CPSES/ CAL TABLE 6-2 O

(Sheet 5)

CONTAINMENT SPRAY HEADER VALVES i

DETAILED DESCRIPTION:

Containment spray header isolation valves open rapidly and may cause the spray pump to run-out if the header is empty.

REFERENCE:

SDAR 85-04 (See Table 6-1, Sheet 14 and Table 8-2, Sheet 14) 1

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CPSES/ CAL TABLE 6-2

(,j (Sheet 6)

DIESEL GENERATOR AIR FILTER B0WL DETAILED DESCRIPTION: The air filter bowl for the emergency diesel generator may rupture.

REFERENCE:

SDAR 85-05 ACTION REQUIRED:

Replace the filter oowl.

STATUS AND SCHEDULE: This action is scheduled to De completed by 4/30/85.

IMPACT: This item will De completed prior to fuel load.

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CPSES/ CAL

, j'N TABLE 6-2 V

(Sheet 7)

CONTROL BOARD MODELING DETAILED DESCRIPTION: Members have been modeled in the seismic analysis I

of the control boards which are not physically present.

REFERENCE:

SDAR 85-10 ACTION REQUIRED: Re-analysis by the vendor, followed by review and t

approval oy TUGC0 is required.

1 STATUS'AND SCHEDULE:

Evaluations are in progress. The expected completion date is 4-29-85.

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IMPACT:

No impact is expected for this item. The conservative design

-of the control boards are expected to accommodate the additional stresses and frequency changes in the model.

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CPSES/ CAL 7.0 INSPECTION REPORTS

7.1 INTRODUCTION

This' chapter' addresses those items that remain open as the result of a Region IV inspection, t

7.2 ACTION ITEMS TUGC0 keeps two action lists of open NRC inspection items. One is kept by the construction Quality Assurance group and the other is kept by the f

operations Technical Support group. These organizations are responsible for assigning responsibility and keeping status on all NRC inspection items.

This section discusses those NRC inspection items for which there

! rebainssignificantactivityonthepartoftheApplicanttoclosethe issue. Also included are inspection items related to CPRT activities.

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Those open inspection items awaiting further action by the NRC staff, such as those items requiring confirmatory reinspections are tracked by the NRC staff and are not contained in this list.

7.3 CONCLUSION

S All NRC inspection report items are being tracked by the NRC staff and TUGCD. All records of these activities are available to and routinely reviewed by the NRC Resident Inspector. New items are added as the NRC inspection program continues.

4 4

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CPSES/ CAL TABLE 7-1 (Q

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INSPECTION REPORTS (Sheet 1 of 35)

ITEM INDEX Title Sheet Deflection and Local Stresses in Pipe Supports

'2 Thermal Expansion Effects in Pipe Supports 3

Stability of Pipe Supports 4

Pipe Stresses From Welded Stachions 5

Post Accident Sampling 6

10CFR21 Procedures 7

Polar Crane 8

Main Coolant System Crossover Leg Restraints 9

Cable Tray Hangers 10 Permanent Security Locks 11 Failure to Provide QC Inspection Criteria and Minimum 12 Separation Failure to Properly Inspect 13 Support Installations 14 Failure to' Notify NRC as Required by 10CFR50.55(e) 15 Water Hammer During Steam Generator Low Level Recovery 16 Natural Circulation Testing 17 Loose Parts Monitor Response Manual 18

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Emergency Response Guidelines and Task Analysis 19 Security Communications 20 Valve Nomenclature on CVCS Diagrams Not Consistent 21 Fire Protection Procedures 22 Surveillance Test Procedures 23 Inadequate Emergency Lighting 24 Fire Alarm Panels 25 Automatic Sprinkler Systems 26 Post-Fire Safe Shutdown Capabilities 27 Emergency Planning News Moderator 28 Valve Line-up Procedure 29 High Range Dosimeter Placement 30 Iodine Monitors 31 Solid Radioactive Waste System 32 Quality Material Storage 33 Maintenance Action Request Procedures 34 35 Control of Measuring and Test Equipment O

CPSES/ CAL TABLE 7-1 (Sheet 2)

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DEFLECTION AND LOCAL STRESSES IN PIPE SUPPORT STRUCTURES DETAILED DESCRIPTION:

Deflection and Local Stresses in Pipe Support Structures. This item is related to CPRT item IX, Design Adequacy of Piping and Supports.

I&E INSPECTION ITEM:

446/8214-04 ACTION REQUIRED: Action complete. CPRT to conduct additional evaluation.

STATUS AND SCHEDULE:

See CPRT item IX, Design Adequacy of Piping and Supports.

IMPACT: Evaluated in CPRT item IX, Design Adequacy of Piping and Supports.

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CPSES/ CAL TABLE 7-1 7)

(Sheet 3)

LJ THERMAL EXPANSION EFFECTS IN PIPE SUPPORTS DETAILED DESCRIPTION:

Differential Thermal Expansion Effects in Wall-to-Wall, Floor to Ceiling and Floor to Floor Wall Pipe Supports.

Modify CCW tunnel floor to ceiling pipe supports. This item is related to CPRT item IX, Design Adequacy of Piping and Supports.

I&E INSPECTION ITEM: 445/8226-03 445/83-12 445/83-07 ACTION REQUIRED: Modify pipe supports in CCW tunnel to remove floor to ceiling connection. Further evaluation to be conducted by CPRT.

STATUS & SCHEDULE: Support modifications are complete.

IMPACT:

Evaluated in CPRT item IX, Design Adequacy of Piping and Supports.

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,'CPSES/ CAL TABLE 7-1 (Sheet 4)

STABILITY OF PIPE SUPPORTS DETAILED DESCRIPTION: Stability of Pipe Supports Designed for CPSES. This item is related to CPRT item IX.b., Stability.

I&E INSPECTION ITEM: 445/8226-03 ACTION REQUIRED:

Evaluation of support designs to De conducted by CPRT.

STATUS AND SCHEDULE:

See CPRT item IX.D., Stability.

IMPACT: Evluation to be conducted by CPRT.

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CPSES/ CAL TABLE 7-1 (Sheet 5)

O PIPE STRESSES FROM WELDED STANCHIONS DETAILED DESCRIPTION: Moment Restraints and Local Pipe Stresses Due to

-Welded Stanchions on Pipes. This is related to CPRT item IX, Design j

Adequacy of Piping and Supports.

I&E INSPECTION ITEM: 445/8226-05 ACTION REQUIRED: Thermal expansion effects in Main Steam Line trunnions evaluated by NRC Special Inspection Team. Additional evaluation to be conducted by CPRT.

STATUS & SCHEDULE:

See CPRT item IX, Design Adequacy of Piping and Supports.

IMPACT:

Evaluation to be completed by CPRT.

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CPSES/ CAL TABLE 7-1 mO (Sheet 6)

POST ACCIDENT SAMPLING DETAILED DESCRIPTION:

NUREG-0737. Item II.F.1-2, Sampling and Analysis of Plant Effluents a)

The Licensee's emergency procedure for providing guidance in post accident sampling (EPP-ll7) is confusing as to specific sampling systems used since all effluent and reactor coolant sample systems appear to be addressed as PASS.

D)

The manual dose assessment procedure EPP-303-draft does not adequately reference source term input from specific grab sample systems, such as the high range effluent grab sample (XRE-5570) A and B sample skid.

I&E INSPECTION ITEM

REFERENCE:

445/8402-04 ACTION REQUIRED:

a)

Revise EPP-ll7, " Post Accident Sampling" b)

Revise EPP-303, " Manual Assessment of Radiological Conditions" STATUS AND SCHEDULE:

a)

EPP-ll7, " Post Accident Sampling", is being revised and will be completed by 5/01/85.

b)

EPP-303, " Manual Assessment of Radiological Conditions", has been revised.

IMPACT:

None. Procedure revisions will occur prior to fuel load.

l CPSES/ CAL TABLE 7-1 (Sheet 7) 10CFR21 PROCEDURES DETAILED DESCRIPTION:

10CFR21 reports received from vendors are reviewed under the 10CFR50.55(e) program during construction. There is not a program to review these reports after CPSES begins operating. This item is related to CPRT item VII.a.5, 10CFR50.55(e) Reportability.

I&E INSPECTION ITEM

REFERENCE:

445/8407-01 ACTION REQUIRED: Revise corporate procedure implementing 10CFR21 requirements.

STATUS AND SCHEDULE:

Corporate procedures will be revised by 5/1/85.

IMPACT: None O

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CPSES/ CAL TABLE 7-1 (Sheet 8)

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POLAR CRANE DETAILED DESCRIPTION:

Gaps on Unit 1 Polar Crane and Seismic Connections Exceed Design Requirements. This item is related to CPRT item VI.b. Polar Crane Shims.

I&E INSPECTION ITEM

REFERENCE:

445/8408-01 ACTION REQUIRED: Reshim containment polar crane platform connections.

STATUS AND SCHEDULE: Action complete. Evaluation to be completed by CPRT.

IMPACT: None

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CPSES/ CAL TABLE 7-1 (Sheet 9) c~)

~a MAIN C0OLANT SYSTEM CROSS 0VER LEG RESTRAINTS DETAILED DESCRIPTION:

Failure to Perform Inspection of Installation Activities Related to Unit 1, Main Coolant Systcm Crossover Leg Restraints.

This item is related to CPRT item V.b, Shortening of Anchor Bolts and CPRT item VII.a.1, Quality Control Inspections.

I&E INSPECTION ITEM

REFERENCE:

445/8408-02 ACTION REQUIRED:

Inspect Main Coolant Loop Crossover Leg Restraint bolting to imbeds.

STATUS AND SCHEDULE:

Inspection complete. Follow up action complete.

IMPACT:

None rx J

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CPSES/ CAL TABLE 7-1 (Sheet 10) p U

CABLE TRAY HANGERS DETAILED DESCRIPTION: Failure to Properly Inspect Cable Tray Hangers.

This is related to CPRT item VIII, Design Adequacy of Cable Tray, Conduit and Supports.

I&E INSFECTION ITEM

REFERENCE:

445/8416-01 ACTION REQUIRED: Evaluate generic implications of this issue through CTH Unit 1 Special Analysis Group.

STATUS AND SCHEDULE: Evaluation in progress.

Issue will be resolved with CPRT item VIII, Design Adequacy of Cable Tray, Conduit and Supports.

IMPACT: See CPRT item VIII, Design Adequancy of Cable Tray, Conduit and Supports.

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CPSES/ CAL TABLE 7-1 (Sheet 11)

PERMANENT SECURITY LOCKS DETAILED DESCRIPTION: This item deals with the installation of permanent security locks within the plant.

I&E INSPECTION ITEM

REFERENCE:

445/8419-04 ACTION REQUIRED:

Install permanent security locks.

STATUS AND SCHEDULE: Permanent security locks will be installed one week prior to fuel load.

IMPACT: None. Action will be completed prior to fuel load.

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CPSES/ CAL TABLE 7-1 (Sheet 12)

O FAILURE TO PROVIDE QC INSPECTION CRITERIA AND MINIMUM SEPARATION DETAILED DESCRIPTION: Separation of some flex conduit from other trains and components was not adequate and inspection criteria was not adequate.

This item is related to CPRT item I.b.1 Flex / Flex Separation and CPRT item I.b.2 Flex / Cable Separation.

I&E INSPECTION ITEM

REFERENCE:

445/8426-01 ACTION REQUIRED:

Investigate all flex conduit and respond to procedural deficiency.

STATUS AND SCHEDULE:

Inspection complete.

IMPACT: Evaluated by CPRT.

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CPSES/ CAL TABLE l-1 (Sheet 13) m

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FAILURE TO PROPERLY INSPECT DETAILED DESCRIPTION:

Several deficiencies in hardware associated with cable tray and pipe hangers were identified. This item is related to CPRT item VII.b.3, Pipe Support / Inspections and item VII.b.6, Electrical Raceway Support Inspections.

I&E INSPECTION ITEM

REFERENCE:

445/8426-02 ACTION REQUIRED:

Correct deficiencies.

STATUS AND SCHEDULE:

Action complete.

IMPACT:

Evaluated by CPRT.

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CPSES/ CAL TABLE 7-1 (Sheet 14) em) v SUPPORT INSTALLATIONS DETAILED DESCRIPTION: Failure of Inspection to Identify Nonconformances in Support Installations. This item is related to CPRT item VII.a.3, Deficiency Reporting Systems.

I&E INSPECTION ITEM

REFERENCE:

445/8434-01 (See CPRT item VII.a.3, Deficiency Reporting Systems)

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CPSES/ CAL TABLE 7-1 (Sheet 15)

FAILURE TO NOTIFY NRC AS REQUIRED BY 10CFR50.55(e)

DETAILED DESCRIPTION:

Failure to Notify NRC as Required by 10CFR50.55(e).

This item is related to CPRT VII.a.5, 10CFR50.55(e) Reportability.

I&E INSPECTION ITEM

REFERENCE:

445/8434-02 ACTION REQUIRED: Review and strengthen procedures.

STATUS AND SCHEDULE:

Action complete.

IMPACT:

CPRT will evaluate.

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CPSES/ CAL TABLE 7-1 1

(Sheet 16) e WATER HAMMER DURING STEAM GENERATOR LOW LEVEL RECOVERY DETAILED DESCRIPTION: Safety Evaluation Report Confirmatory Issues Section 10.4.7 - The licensee has not demonstrated the ability to recover from a low-level water transient without causing an unacceptable feedwater/ steam generator water hammer.

I&E INSPECTION ITEM

REFERENCE:

445/8436-02 ACTION REQUIRED:

No additional testing is required at CPSES.

NRR close issue with Region IV.

STATUS AND SCHEDULE: This item has been reviewed with NRR and verbally accepted. TUGC0 commitment to be clarified between NRR and Region IV NRC personnel.

IMPACT:

None on fuel load.

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CPSES/ CAL TABLE 7-1 (Sheet 17)

'N NATURAL CIRCULATION TESTING DETAILED DESCRIPTION: Safety Evaluation Report Confirmatory Issues Section 5.4.3 - The licensee has not submitted adequate justification for referencing other plant natural circulation cooldown tests.

I&E INSPECTION ITEM

REFERENCE:

445/8436-04 ACTION REQUIRED:

Submit additional justification for referencing other plant natural circulation cooldown tests.

(See Table 5-2, Sheet 7)

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CPSES/ CAL TABLE 7-1 O'

(Sheet 18)

LOOSE PARTS MONITOR RESPONSE MANUAL DETAILED DESCRIPTION: Safety Evaluation Report Confirmatory Issues Section 5.5.5 - The licensee has not provided a response manual for the Loose Parts Monitoring System.

I&E INSPECTION ITEM

REFERENCE:

445/8436-05 ACTION REQUIRED:

This item is under engineering review. A procedure will address this item.

STATUS AND SCHEDULE: This procedure will be completed by 5/15/85.

IMPACT:

None O

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4 TABLE 7-1 p

(Sheet 19) i V

EMERGENCY RESPONSE GUIDELINES AND TASK ANALYSIS

[

i DETAILED DESCRIPTION:

None of the Emergency Response Guidelines (ERGS) reviewed included an approved task analysis package.

I&E INSPECTION ITEM

REFERENCE:

445/8436-07 i.'

ACTION REQUIRED: Generate task analysis package. This is a backfit requirement.

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(See Table 5-3, Sheet 9)

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CPSES/ CAL TABLE 7-1 Q

(Sheet 20)

SECURITY COMMUNICATIONS DETAILED DESCRIPTION: TUGC0 has committed to the implementation of an improved communications system.

I&E INSPECTION ITEM

REFERENCE:

445/8437-01 ACTION REQUIRED:

Upgrade communications systems.

STATUS AND SCHEDULE:

Upgrade to oe completed by 7/30/85 contingent on approval of the FCC license application.

IMPACT:

None (See also Table 6-1, Sheets 27 and 28)

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CPSES/ CAL TABLE 7-1 (Sheet 21)

VALVE NOMENCLATURE ON CVCS DIAGRAMS NOT CONSISTENT DETAILED DESCRIPTION: The nomenclature for valve prefixes on the CVCS diagrams are not consistent.

I&E INSPECTION ITEM

REFERENCE:

446/8439-02 ACTION REQUIRED:

Revise procedures.

STATUS AND SCHEDULE: Procedure revision will be completed by 5/10/85.

IMPACT: None O

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CPSES/ CAL TABLE 7-1 nV (Sheet 22)

FIRE PROTECTION PROCEDURES DETAILED DESCRIPTION:

Deficiencies with various Fire Protection Procedures need to be corrected.

1&E INSPECTION ITEM

REFERENCE:

445/8444-01 ACTION REQUIRED:

Revise procedures.

STATUS AND SCHEDULE: Procedure revisions will be complete by 5/15/85.

IMPACT:

None. Procedures will De updated by fuel load.

(See also Table 5-1, Sheet 5)

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CPSES/ CAL p

TABLE 7-1 v

(Sheet 23)

SURVEILLANCE TEST PROCEDURES DETAILED DESCRIPTION:

Some discrepancies exist between surveillance test procedures and the latest revision to Tech Specs.

I&E INSPECTION ITEM

REFERENCE:

445/8444-02 ACTION REQUIRED:

Revise procedures.

STATUS AND SCHEDULE:

Procedure revision will be completed by 5/01/85.

IMPACT: None OL]

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CPSES/ CAL TABLE 7-1 O

(Sheet 24)

INADEQUATE EMERGENCY LIGHTING DETAILED DESCRIPTION: There are insufficient battery pack lights of 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> rating in several areas.

I&E INSPECTION ITEM

REFERENCE:

445/8444-04 ACTION REQUIRED: Provide additional battery packs.

(See Table 6-1, Sheet 2 and also Table 5-1, Sheet 5)

O O

CPSES/ CAL TABLE 7-1 O

(Sheet 25)

FIRE ALARM PANELS DETAILED DESCRIPTION: Fire alarm control panels are not listed according to paragraph 2022 of NFPA 72D.

I&E INSPECTION ITEM

REFERENCE:

445/8444-06 (See Table 5-1, Sheet 5 and also Table 6-1, Sheet 4) lO l

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CPSES/ CAL TABLE 7-1 O'

(Sheet 26)

AUTOMATIC SPRINKLER SYSTEMS DETAILED DESCRIPTION: Automatic sprinkler systems in some areas do not meet the ceiling-sprinkler head maximum clearance of NFPA-13.

I&E INSPECTION ITEM

REFERENCE:

445/8444-07 ACTION REQUIRED:

Show the intent of NFPA-13 is met or move sprinkler heads closer to the ceiling.

STATUS ~AND SCHEDULE: All sprinkler modifications are complete. An analysis justifying non-standard placement of sprinkler heads in certain fire areas was submitted to NRR by letter TXX-4422 dated 2/19/85.

IMPACT: There is no impact en the safe operation of CPSES Unit I while NRR reviews the TUGC0 submittal.

(See also Table 5-1, Sheet 5 and Table 8-1, Sheet 8)

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I CPSES/ CAL 1

TABLE 7-1 q-ig (Sheet 27)

POST-FIRE SAFE SHUTDOWN CAPABILITIES DETAILED DESCRIPTION: The inspection report in this area could not ce completed because the applicant was still reviewing, analyzing and revising key documents in the Appendix R comparison backfit.

The applicant has not finalized the Appendix R backfits required. Some areas in question are the CVCS Charging System, Letdown System, Boric Acid Tanks, Pressurizer PORVs, Main Steam Isolation Valves, and CCW Surge Tank.

Other findings are related to Appendix R, III.G.2 compliance for fire areas AA and SK, where some apparent Appendix R discrepancies were identified.

The applicant's safe shutdown procedures were incomplete and cannot be finalized until the Appendix R analysis is complete.

Finally, the associated circuits concern was not adeauately addressed for the Common Bus 1

and Spurious Signals issues.

This is considered an unresolved item pending completion of all analyses, document revisions, procedures and resolution of any deviations as well as a review of all anlayses and documents by Auxiliary Systems Branch - NRR i

and completion of the NRC inspection effort, I&E INSPECTION ITEM

REFERENCE:

445/8444-08

'd (See Table 5-1, Sheet 5 and also Table 6-1, Sheets 25 and 26) l O

CPSES/ CAL TABLE 7-1

, -w, (Sheet 28)

U EMERGENCY PLANNING NEWS MODERATOR DETAILED DESCRIPTION:

Consider appointing a news media /puolic affairs professional to act as moderator.

I&E INSPECTION ITEM

REFERENCE:

445/8441-04 ACTION REQUIRED: Evaluation this cons'ideration.

STATUS AND SCHEDULE:

Evaluation underway.

Determination will be made in August 1985.

IMPACT:

None s

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CPSES/ CAL TABLE 7-1

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(Sheet 29)

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VALVE LINE-UP PROCEDURES DETAILED DESCRIPTION: Actions are needed to preclude valve lineup problems and to ensure that all such problems are documented in a timely manner by the Shift Supervisors with first-hand knowledge of the problems.

I&E INSPECTION ITEM

REFERENCE:

445/8445-01 ACTION REQUIRED:

Correct deficiencies such that these types of problems do not reoccur.

1 STATUS AND SCHEDULE: Valve hand wheels have been labeled. Shift supervisor additional training requirements are under evaluation. Action to be completed by 6/21/85.

IMPACT:

None.

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CPSES/ CAL TABLE 7-1 (Sheet 30)

HIGH RANGE DOSIMETER PLACEMENT DETAILED DESCRIPTION:

Discrepancy regarding the number of high range dosimeters in the OSC annex.

I&E INSPECTION ITEM

REFERENCE:

445/8333-56 and 446-8317-56 ACTION REQUIRED:

Revise EPP-107, " Maintenance and Inventory of Emergency Equipment and Supplies", and HPT-801, " Operation of Portable Survey Instruments".

STATUS AND SCHEDULE: These procedures will De revised by 6/28/85.

IMPACT:

No impact to 5% power.

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CPSES/ CAL TABLE 7-1 (Sheet 31)

IODINE MONITORS DETAILED DESCRIPTION:

Place iodine monitors in appropriate emergency response facilities.

I&E INSPECTION ITEM

REFERENCE:

445/8333-57 and 446-8317-57 ACTION REQUIRED: Monitors reliability must be established and procedures revised to accommodate alarm settings, alarm response, etc.

STATUS AND SCHEDULE: These items will be completed by 6/28/85.

IMPACT:

No impact to 5% power.

O O

CPSES/ CAL TABLE 7-1 (Sheet 32)

SOLID hADI0 ACTIVE WASTE SYSTEM DETAILED DESCRIPTION:

Complete preoperational tests on Solid Radioactive Waste System.

I&E INSPECTION ITEM

REFERENCE:

445/8314-06 and 446/8308-06 ACTION REQUIRED: TUGC0 will need to revise the FSAR, make a vendor selection, and submit the process control program for a mobile solidification system to the Commission for approval prior to exceeding 5%

power.

STATUS AND SCHEDULE: The FSAR was revised by Amendment 54 of 1/21/85. The revised CPSES Process Control Program was suomitted to the NRC by TXX-4391 of 1/7/85. A vendor will De selected and his equipment tested onsite prior to exceeding 5% power.

IMPACT:

No safety significance.

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CPSES/ CAL TABLE 7-1 (Sheet 33)

QUALITY MATERIAL STORAGE DETAILED DESCRIPTION:

Non-quality material was stored with quality material in a "Q" material hold area of the maintenance building.

I&E INSPECTION ITEM

REFERENCE:

445/8431-07 ACTION REQUIRED: Training will be provided to Maintenance personnel to assure that they recognize the dissimilarities between "Q" material hold areas and "Q" material storage and staging areas.

STATUS AND SCHEDULE: The training will be completed by 05/01/85.

IMPACT: None.

O O

CPSES/ CAL TABLE 7-1 (Sheet 34)

O MAINTENANCE ACTION REQUEST PROCEDURES DETAILED DESCRIPTION: Various procedural inadequacies were cited in procedures governing maintenance action requests (MARS), temporary modifications, design control and record retention.

I&E INSPECTION ITEM

REFERENCE:

445/8431-08 ACTION REQUIRED: Affected procedures will be revised to address these i

concerns. Also, emergency modifications will be processed through station engineering as normal modifications until design control procedure revisions are complete.

STATUS AND SCHEDULE:

Procedure revisions will be completed by 06/01/85.

i IMPACT:

None.

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CPSES/ CAL TABLE 7-1 (Sneet 35)

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CONTROL OF MEASURING AND TEST EQUIPMENT DETAILED DESCRIPTION:

Control and calibration of measuring and testing equipment was not adequately established, including assignments of 4

responsibility for equipment checkout and transportation.

I&E INSPECTION ITEM

REFERENCE:

445/8431-14 ACTION REQUIRED: STA-608, " Control of Measuring and Test Equipment", is being revised to address the concerns of this violation.

STATUS AND SCHEDULE: The procedure revision will be complete by 5/31/85.

l IMPACT:

None. Procedures will be revised prior to fuel load.

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CPSES/ CAL 8.0 PRE 0PERATIONAL TESTING

8.1 INTRODUCTION

This chapter addresses the status of Preoperational Testing.

Preoperational test deferrals that have already been approved by the NRC, as identified in SSER #6, are not included in this chapter.

8.2 ACTION ITEMS _

Table 8-1 lists all preoparational tests not yet complete, some of which may require deferral beyond fuel load. Where necessary, requests for deferral will suomitted to the NRC with appropriate justifications.

8.3 CONCLUSION

The bulk of preoperational testing activities has been satisfactorily completed. The few remaining activities will be completed prior to fuel

({])

load or a justification for deferral will ne provided to the NRC..

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8-1

CPSES/ CAL i

TABLE 8-1

.O eREoeERArloaAL TESTS (Sheet 1 of 16)

ITEM INDEX l

Title Sheet Control Room Pressurization Retest 2

Diesel Generator Load Test 3

ERF Computer Retest 4

Fire Detection 5

i Control Room Filtration Retest 6

Solid State Isolation Cabinets 7

Fire Protection 8

Primary Plant Ventilation System 9

Auxiliary Building Ventilation Systems 10 Containment Spray System Response Time 11 Gai-tronics Audibility 12 Main Steam _ Isolation Bypass Valves Actuators 13 Diesel Generator Minimum-Maximum Excitation 14 i

Limiters.

Containment Spray Valves 15 Radiation Monitoring Report Processor 16 L0 J

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CPSES/ CAL TABLE 8-1 (Sheet 2)

CONTROL ROOM PRESSURIZATION DETAILED DESCRIPTION: A pressure equalization path is oeing installed in the wall separating the Control Room from the Mechanical Equipment Room to facilitate proper ventilation in this area. A pressurization test of the Control Room complex will be conducted upon completion of the vent path.

REFERENCE:

FSAR Table 14.2-2 Sheet E3.

ACTION REQUIRED:

Complete the Control Room pressurization test (PT-07-02 RT-1).

STATUS AND SCHEDULE: Scheduled for completion by 5/15/85.

IMPACT: Tnis test is expected to be completed prior to fuel load.

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CPSES/ CAL TABLE 8-1 Q

(Sheet 3)

DIESEL GENERATOR LOAD TEST DETAILED DESCRIPTION: Verify that each Diesel Generator is capable of satisf actorily handling short and long term maximum loads as described in Table 6-1, Sheet 9.

Also, verify that the diesel is capable of being loaded within the required time period of 10 seconds after a start signal.

REFERENCE:

FSAR Table 14.2-2, Sheet 34 ACTION _ REQUIRED:

Complete load test.

(lCP-PT-29-03 RT-3)

STATUS AND SCHEDULE: Awaiting NRC staff approval to perform a 100%

H ucity load test. Testing will be performed within two weeks of receiving approval.

IMPACT: This test is expected to be performed prior to fuel load.

("N (Also see Table 6-1, Sheet 9)

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1 CPSES/ CAL TABLE 8-1 O

(Sheet 4)

ERF COMPUTER SYSTEM INPUT VERIFICATION DETAILED DESCRIPTION: Verify correct response of the Emergency Response Facility Computer to each analog and digital input signal after I

completing actions described in Table 6-1, Sheet 33.

1

REFERENCE:

ACTION REQUIRED:

Complete verification (1CP-PT-78-01 RT-1)

STATUS AND SCHEDULE:

Schedule for test completion 6/28/85.

IMPACT: This test is expected to be performed prior to fuel load.

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(Also see Table 6-1, Sheet 33) i f

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CPSES/ CAL TABLE 8-1

' (d,-

(Sheet 5)

FIRE DETECTION DETAILED DESCRIPTION: Verify operation of the Plant Fire Detection System and operation of Engineered Fire Protection Devices (Halon i

System, door and damper closure).

REFERENCE:

FSAR Table 14.2-2, Sheet 8 ACTION REQUIRED:

Complete verification (1CP-PT-06-03 Rev. 1)

STATUS AND SCHEDULE:

Scheduled for completion of testing by 9/20/85.

IMPACT: This item will be complete prior to fuel load or justification for deferral will be submitted to the NRC.

(Also see Table 5-1, Sheet 5 and Table 6-1, Sheet 4)

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CPSES/ CAL TABLE 8-1 1

(~)

(Sheet 6) x./

CONTROL ROOM FILTRATION SYSTEM FILTER DETAILED DESCRIPTION:

Verification of proper filter installation by an in-place leak test of the Control Room Filtration System HEPA and HECA filters, including verification that there are no leaks in the frame or housing, no bypassing of filter, and no damage to filter.

REFERE N,CE_:

Reg. Guide 1.52, Rev. 2 FSAR Section 6.4, 9.4.1, 12.3.3, 15.6.5.4 (4)

FSAR Table 14.2-2 Sheet 28 ACTION REQUIRED:

Complete the Control Room Filtration System Filter test. (1CP-PT-07-03 RT-1)

STATUS AND SCHEDULE:

Scheduled for test completion oy 6/28/85.

IMPACT: Tnis test is expected to De performed prior to fuel load.

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CPSES/ CAL TABLE 8-1

()

(Sheet 7)

SOLID STATE ISOLATION CABINETS DETAILED DESCRIPTION: Voltage sensing relays in the solid state isolation cabinets have failed on several ocassions.

REFERENCE:

MDB-8304-0118S FSAR Sections 7.1.2.6 and 8.3.1.2.1 ACTION REQUIRED:

Replace failed relays with relays of a different design and verify correct operation.

STATUS AND SCHEDULE: Relay delivery scheduled for 5/31/85. Retest of isolation cabinets scheduled for two weeks after delivery.

IMPACT: This item is expected to be completed prior to fuel load.

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CPSES/ CAL TABLE 8-1

-O (Sheet 8)

FIRE PROTECTION DETAILED DESCRIPTION: Verify the operability of the sprinkler system modificat.ons for the Auxiliary Building elevation 852.

REFERENCE:

FSAR Table 14.2-2, Sheet 8.

ACTION REQUIRED: Verify operability of modified system.

STATUS AND SCHEDULE:

Schedule for completion 7/26/85.

IMPACT: This item will be completed prior to fuel load or justification for deferral will be submitted to the NRC.

(Also see Table 5-1, Sheet 5 and Taole 7-1, Sheet 26)

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CPSES/ CAL TABLE 8-1 O

(Sheet 9)

PRIMARY PLANT VENTILATION SYSTEM DETAILED DESCRIPTION:

This item requires the rebalancing of the Primary Plant Ventilation (PPV) System, the rebalancing of the Auxiliary, Fuel, and Safeguards Buildings and verification that the Auxiliary, Safeguards and Fuel Buildings can be maintained at

.10 inches H 0.

2

REFERENCES:

FSAR Table 14.2-2, Sheet 29 FSAR Section 9.4.1.4 ACTION REQUIRED:

Complete the PPVS Air Balance, the Auxiliary, Safeguards and Fuel Building air balance, then verify that the Auxiliary, Safeguards and Fuel Buildings can be maintained at

.10 inches H 0.

2 STATUS AND SCHEDULE: The system design changes and the retesting are estimated to De completed oy 7/85.

IMPACT: This item will De completed prior to fuel load or justification O'

for deferral will De submitted to the NRC.

(Also see Table 6-1, Sheets 6 and 11)

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CPSES/ CAL TABLE 8-1 n()

(Sheet 10)

AUXILIARY BUILDING VENTILATION SYSTEM DETAILED DESCRIPTION: Verify correct flow balance as shown on diagram 2323-M1-0304-01, Rev. CP-6, for the Auxiliary Building Ventilation Supply and Exhaust System for the office and service area that exhausts into the Primary Plant Ventilation System.

REFERENCES:

FSAR Section 9.4.1.4.

FSAR Taole 14.2-2, Sheet 29 Technical Specification 3/4.11.2 ACTION REQUIRED:

Irtcorporate design changes and rebalance the Primary Plant Ventilation S) stem.

STATUS AND SCHEDULE:

Estimated completion date 7/1/85.

IMPACT: This item will be completed prior to fuel load or justification for deferral Will be submitted to the NRC.

(Also see Table 6-1, Sheets 6 and 11)

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CPSES/ CAL TABLE 8-1 O

(Sheet 11)

CONTAINMENT SPRAY SYSTEM RESPONSE TIME DETAILED DESCRIPTION:

Data analysis of the response time testing indicates that the response time for Containment Spray Actuation exceeds the required time as stated in the CPSES Technical Specification.

REFERENCES:

Technical Specification 3.3.2, Table 3.3-5 FSAR Table 14.2-2, Sheet 42 ACTION REQUIRED: Submit a request to change Technical Specifications.

STATUS AND' SCHEDULE: Technical Specification change request will be submitted to the NRC by 5/15/85.

IMPACT: This item is expected to be completed prior to fuel load.

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CPSES/ CAL TABLE 8-1 O-(Sheet 12)

GAI-TRONICS AUDIBILITY DETAILED DESCRIPTION: Audibility of the Gai-tronics Intraplant Public Address System and the Emergency Evacuation Alarm. System, failed the required audibility levels in those areas in excess of 100 dB background noise.

REFERENCES:

FSAR Section 9.5.2.2 FSAR Table 14.2-2, Sheets 40A and 60 ACTION REQUIRED: Warning lights will De installed in the excessive noise areas. Lights to be tested after installation.

STATUS AND SCHEDULE:

Estimated completion date 7/1/85.

IMPACT: This item will be completed prior to fuel load or justification for deferral will be submitted to the NRC.

(Also see Table 6-1, Sheet 5) l 1

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CPSES/ CAL TABLE 8-1 fT d

(Sheet 13)

MAIN STEAM ISOLATION BYPASS VALVES ACTUATORS DETAILED DESCRIPTION: Verify that the Manual Main Steam Isolation Bypass Valves Actuators function correctly as described in Table 6-1, Sheet 10.

REFERENCES:

FSAR Table 14.2-2, Sheet 50 ACTION REQUIRED:

Upon NRC approval of changes referenced in Table 6-1, Sheet 10, verify operation of manual actuators after installation.

STATUS AND SCHEDULE: Estimated completion date 6/15/85.

l IMPACT: This item is expected to be completed prior to fuel load.

(Also see Table 6-1, Sheet 10)

O O

CPSES/ CAL TABLE 8-1 O

(Sheet 14)

DIESEL GENERATOR MINIMUM-MAXIMUM EXCITATION LIMITERS DETAILED DESCRIPTION: Verify that the diesel generator minimum / maximum excitation limiters will function correctly.

REFERENCES:

Specification MS-34 ACTION REQUIRED: Test minimum / maximum excitation limiters.

STATUS AND SCHEDULE: See Delow IMPACT: The diesel generators are completely operable without the minimum / maximum excitation limiters. They are only operability enhancers. Scheduling of this item does not impact fuel load.

(Also see Table 6-1, Sheet 8) 1 l

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CPSES/ CAL TABLE 8-1

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(Sheet 15)

CONTAINMENT SPRAY VALVES DETAILED DESCRIPTION: Verify that containment spray valves, 1-HV-4776 and 1-HV-4777 have an opening time long enough to avoid tripping the containment spray pump motors.

REFERENCES:

FSAR Table 14.2-2, Sheet 18 FSAR Sections 6.2.2, 6.5.2, 15.6.5 Technical Specification 3/4.6.2, Table 3.6-1 ACTION REQUIRED:

After completion of activities required by Table 6-1, Sheet 14, verify that both valves (1-HV-4776 and 1-HV-4777) open within the new required opening times without tripping the containment spray pumps.

STATUS AND SCHEDULE:

See below IMPACT: This item will be completed prior to fuel load or justification

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for deferral will be submitted to the NRC.

(Also see Table 6-1, Sheet 14) r O

CPSES/ CAL TABLE 8-1 pd (Sheet 16) s RADIATION MONITORING REPORT PROCESSOR DETAILED DESCRIPTION: Tnis item requires the resolution of the interface problem between the DEC operating system and the Kennedy Tape Drive unit and the subsequent retesting. The tape drive unit is not necessary for normal operations of the unit. The ability to use the Kennedy Tape Drive unit will increase confidence in the satisfactory operation and reliability of the radiation report processor system.

REFERENCES:

FSAR Sections 11.5, 12 and 17A ACTION REQUIRED: Resolve the interface problem, implement the resolution and perform a Radiation Monitoring Report Processor test.

STATUS AND SCHEDULE: See below IMPACT:

Backup of the system may be accomplished without the Kennedy unit. The radiation monitoring report processor meets all operational O-requirements without the performance of this test.

Scheduling of this item does not impact fuel load.

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CPSES/ CAL 9.0 OPERATIONS O,

9.1 INTRODUCTION

This chapter addresses those actions which relate to the operation and maintenance of CPSES Unit 1.

9.2 ACTION ITEMS 9.2.1 OPERATIONS PHASE PROGRAMS All adrainistrative and technical programs required,for the safe and efficient operation of CPSES are currently in place and functioning and have undergone all required internal and external reviews. These 3

programs include methods for the routine identification, evaluation, tracking and implementation of work items which arise during the normal course of plant operations.

Programs have been in operation for some time for the handling of Maintenance Action Requests, Deficiency aV Reports, Nonconformance Reports, Station Modification Requests, Problem Reports, and Corrective Action Requests. All work items being identified and tracked under these programs are being resolved in a routine ongoing manner. There are no major items in these areas which require formal submittal to the NRC staff for review or which would inpact on the ability to load fuel or operate the plant safely during any phase of the operating cycle.

4 9.2.2 PRE-FUEL LOAD REVIEWS Reviews are performed on a regular basis by the plant operations and technical support staff to deter.nine the impact of existing work items on fuel load and subsequent plant operations.

Prior to fuel load, final reviews will De performed by the Station Operations Review Committee (S0RC) and the Operations Review Committee (0RC) to confirm that there are no significant work items which could affect the ability to safely load fuel and operate the plant.

1 9-1

CPSES/ CAL Also, an operational readiness review report will be prepared for the

-TUGC0 Vice President, Nuclear Operations. This report will provide a comprehensive overall readiness assessment of the Nuclear Operations organization and associated support groups to assume responsibility for fuel load and operation of CPSES Unit 1.

9.3 CONCLUSION

S There are currently no significant work items relating to plant operations phase activities which would impact the ability to load fuel and safely operate the plant through all phases of operation. Any new work items which are identified as part of normal ongoing inspections or reviews will De assessed and resolved as they occur using existing plant administrative and technical programs.

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CPSES/ CAL 10.0 TECHNICAL SPECIFICATIONS

10.1 INTRODUCTION

This chapter addresses the actions that must be completed and resolved to allow the issuance of a complete and adequate set of technical specifications for CPSES Unit 1.

NRC review of the draft CPSES Technical Specifications began in 1932.

In April 1984, Enercon Services was hired by CPSES to provide guidance for CPSES personnel performing a comprehensive review of the draft Technical Specifications.

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The CPSES Final Draft Technical Specifications were issued by NRR letter of September 4, 1984.

NRC changes to the final draft were issued by NRR letter of October 19, 1984. These changes incorporated CPSES comments as suomitted oy letter TXX-4274 of August 20, 1984.

An on-going review of the CPSES Technical Specifications will continue as the plant is readied for operation.

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10.2 ACTION ITEMS The ongoing CPSES review resulted in additional proposed changes to the Final Draft Technical Specifications which were sent to the NRC (see Table 10-1). This last submittal is currently undergoing NRC review.

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The NRC issued additional questions which resulted from the Reactor Systems Branch review of the CPSES Technical Specifications.

CPSES has responded to these questions (see Table 10-1) and this response is i

currently undergoing NRC review, 10.3 CONCLUS I,0N,S_

i The CPSES review of the Final Draft Technical Specifications is t

essentially complete rid approval of the proposed changes is required by l

the staff.

CPSES will continue to review the technical specifications

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t; until fuel load. Any further proposed changes resulting from the on-going. review will be. submitted to the NRC as identified. Prior to the j

issuance of the Unit 1 Operating License, an affirmation of correctness

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. i of the, Unit'l Technical Specifications will be submitted to the NRC.

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CPSES/ CAL TABLE 10-1 Q

TECHNICAL SPECIFICATION ITEMS (Sheet 1 of 3)

ITEM INDEX Title Sheet CPSES Proposed Changes to Final Draf t 2

Technical Specifications NRC Reactor Systems Branch Questions 3

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CPSES/ CAL TABLE 10-1 (Sheet 2)

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CPSES PROPOSED CHANGES TO FINAL s-DRAFT TECHNICAL SPECIFICATIONS DETAILED DESCRIPTION: The CPSES proposed changes to the Final Draft Technical Specifications include changes resulting from the ongoing comparison review of CPSES to the Final Draft.

SER/SSER

REFERENCE:

See also SER, Section 16 and SSER #6, Section 16.

ACTION REQUIRED:

NRC review CPSES proposed changes.

NRC revise CPSES Technical Specifications.

STATUS AND SCHEDULE:

The CPSES proposed changes were submitted by TXX-4360 of 11/15/84.

IMPACT:

This item is sufficiently complete such that there should be no impact on any phase of operation of CPSES Unit 1.

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CPSES/ CAL TABLE 10-1 (Sheet 3)

NRC REACTOR SYSTEMS BRANCH QUESTIONS DETAILED DESCRIPTION: Additional questions concerning the CPSES Technical Specifications were issued as a result of the NRC Reactor Systems Branch (RSB) review.

SER/SSER

REFERENCE:

See also SER, Section 16 and SSER #6, Section 16.

ACTION REQUIRED:

NRC review CPSES response to RSB questions. NRC revise CPSES Technical Specifications.

STATUS AND SCHEDJLE: The CPSES response to NRC letter of 10/5/84 was submitted by TXX-W 31 of 4/9/85.

IMPACT: This item is sufficiently complete such that there should be no impact on any phase of operation of CPSES Unit 1.

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CPSES/ CAL 11.0 MISCELLANE0US

11.1 INTRODUCTION

This chapter addresses miscellaneous activities required to complete the licensing process for CPSES Unit 1 that are not addressed in another chapter of this report.

11.2 ACTION ITEMS Miscellaneous action items are listed in Table 11-1.

11.3 CONCLUSION

S All miscellaneous action items are sufficiently complete to allow granting of an Operating License for CPSES Unit 1.

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4 CPSES/ CAL TABLE 11-1 i

j h MISCELLAhE0US ACTIVITIES 4

(Sheet 1 of 3) 4 I

ITEM INDEX i

Title Sheet ij' Environmental Protection Flan 2

i Emergency Plan Implementation 3

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CPSES/ CAL TABLE 11-1 (Sheet 2)

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ENVIRONMENTAL PROTECTIUN PLAN DETAILED DESCRIPTION: The NRC staff reviewed the CPSES Environmental Impact Riport and by letter dated Fe' ruary 21, 1984 issued a Draft o

Environmental Plan for CPSES Units 1 and 2.

CPSES provided comments to 2

this draft by letter dated April 6, 1984.

ACTION REQUIRED:

NRC staff to issue Final Environmental Protection Plan for Units 1 and 2 as Appendix B to the CPSES Operating Licenses.

STATUS AND. SCHEDULE:

This item is complete except for issuance of Final Environmental Protection Plari.

l-IMPACT: This item is sufficiently canplete such that there should be no impact on any phase of operation of CPSES Unit 1.

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CPSES/ CAL TABLE 11-1 nV (Sheet 3)

EMERGENCY PLAN IMPLEMENTATION DETAILED DESCRIPTION: The CPSES Emergency Plan must be in effect for the operation of CPSES Unit 1.

ACTION REQUIRED: TUGC0 must implement the Emergency Plan and so notify the NRC staff.

STATUS AND SCHEDULE: The Emergency Plan will be implemented snortly before fuel load.

IMPACT: This item is sufficiently complete such that there should be no impact on any phase of operation of CPSES Unit 1.

Minor activities relating to the emergency plan are listed below:

1.

Alert and Notification Test Includes the testing of sirens to verify operability and a phone survey to determine effectiveness. ECD 4/85 i) 2.

NRC to review and accept personnel accountability system.

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Amend Emergency plan to include procedure / plan cross reference.

7/85 4.

Prepare surveillance procedure to periodically test sound powered phones and evacuation alarm signal. ECD 7/85 5.

Post-implementation review of Emergency Response Facility and any resulting modifications. ECD-after implementation.

6.

Iodine monitors to be reliability checked and revise procedures to accommodate alarm settings and alarm responses.

ECD 4/85.

7.

Develop procedure for core damage assessment using Westinghouse generic methodology. ECD 7/85.

These activities will be resolved and do not affect the acceptability of the Emergency Plan. None of these items will prevent TUGC0 from implementing the Emergency Plan, which has been successfully exercised

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