ML19260C442
| ML19260C442 | |
| Person / Time | |
|---|---|
| Issue date: | 05/31/1978 |
| From: | Graves C, Ross D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19260C441 | List: |
| References | |
| REF-GTECI-A-01, REF-GTECI-PI NUDOCS 8001030361 | |
| Download: ML19260C442 (17) | |
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ENCLOSURE 1
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Task A-1
-e WATER HAM 4ER Lead NRR Organization:
Division of Systems Safety (DSS)
Lead Supervisor:
D. F. Ross,.Jr.
A/D for Reactor Safety, DSS Task Manager:
Charles C. Graves, RS8/ DSS Applicability:
Light Water Reactors Projected Completion Date:
June 22, 1979 l
9 1700 301 ig 39 p,0 p
Task A-1
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Rev. No. 1 May 1978 1.
DESCRIPTION OF PROBLEM Since 1971 there have been about one hundred incidents involving water hammers in BWRs and PWRs have been reported. The water hammers (or steam hammers) have involved steam generator feedrings and piping, the RHR system, ECC systems, and containment spray, service water, feedwater and steam lines. The incidents have been attributed to such causes as rapid condensation of steam pockets, steam-driven slugs of water, pump startup with partially empty lines, and rapid valve action. Most of the damage reported has been relatively minor, involving pipe hangers and restraints; however, there have been severai incidents which have resulted in piping and valve damage.
No water hammer incident has resulted in the release of radioactivity outside of the plant. However, because of the continuing incidence of water hammer events, the number of phenomena, and the potential safety significance of the systems involved, systematic review proce-dures should be developed to ensure that water hammer is given appro-priate consideration in CP and OL licensing reviews and in reviews of operating reactors. There is also a need for systematic investigations.
of potential water hammer phenomena to obtain information to be used in providing guidance for the licensing review process and developing NRC positions on water hammer for use in the SRP. These investigations will also provide guidance and methods for understanding and resolving water hammer problems in existing plants.
2.
PLAN FOR PROBLEM RESOLUTION The overall program for resolution of the water hammer issue is divided into four tasks.
Task 1 Water Hammer Summary Reports Under this task the initial and final summary reports on water hammer will be prepared.
Task 1.1 Water Hammer Report by DOR / DSS Technical Review Group An interdivisional (DOR / DSS) Technical Review Group on Water Hammer Phenomena was established on March 10, 1977.
In accordance with its charter, this group will prepare a report that will " review operating experience and analytical investigations to date, place the safety significance of water hammer phenomena in nuclear plants in perspective, and summarize the current staff position regarding 1700 302 A-1/1
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Task A-1 Rev. No. 1 May 1978 water hammer phenomena for CP and OL reviews and reviews of operating plants." A draft of this report has been prepared.
Extensive revisions of the draft will be made prior to its submission for approval at the Assistant Director and Director levels. The report will provide input for Tasks 2.0, 3.0 and 4.0.
Task 1.2 Final Sumary Report on Water Hammer A NUREG report will be prepared which summarizes the results of this Category A task on water hammer.
Task 2 Revision of CP and OL Review Procedures The objective of this task is to develop systematic review precedures concerning water hammer for use in the CP and OL review process.
The Standard Format and Standard Review Plan will be revised to require the applicant, as appropriate, to:
(1) address potential water hammer problems in various systems; (2) demonstrate that there are adequate design features and operating procedures to prevent damaging water hamer events; and (3) expand the preopera-tional testing program to include verification that these design features and operating procedures do prevent damaging water hamer events.
In addition, guidance for the licensing review process will be prepared in the form of Branch Technical Positions for steam generators, feedwater systems and other systems, where required.
Requests for preparation or modification of Regulatory Guides and changes to the Standard Technical Specifications will also be made under this task.
In view of the relas rely short time scale of the overall water hammer task, performance of the task objectives will not be keyed to the issuance of new or modified Regulatory Guides.
However, SD will be contacted at an early stage to permit them to make changes in manpower plans for work on the guides.
Work accomplished under this task will be based on the Task 1.1 report and the information developed under Task 4.0.
Branches assigned primary review responsibility in the SRP will have the responsibility for all revisions to a given section of the SRP and the corresponding section of the Standard Format. This will include the responsibility for obtaining concurrence of any other branch assigned a secondary review or coordination responsibility in the given section of the SRP.
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Task A-1 Rev. No. 1 May 1978 Task 3 Water Hamer Positions for Operating Reactors,
Task 3.1 Short-Tem Position The DOR / DSS technical review group concluded that continued short-term plant operation is justified in view of the low probability of a water hammer esulting in unacceptable consequences. However, the staff alst concluded that a particular type of water hamer, namely that du e to the rapid condensation of steam in feedwater lines of PWRs,,present:; the most imediate potential safety concern and that further actions by licensees were warranted to assure that an acceptably low risk to public safety is maintained. This is appropriate since steam generator feedwater line water hamers are well enough understood at this time to permit staff action. Accord-ingly, a generic position addressing this concern is being developed by DOR for operating plants and will be transmitted to affected licensees. A request for licensee prcposed plant modifications to eliminate this concern and a more comprehensive reporting of water hamer events in the future will be included.
Task 3.2 Long-Term Position Following completion of Tasks 2.0 and 4.0 and based on further data from operating plants, an assessment will be made of the need for any further requirements to be imposed on operating plants for other types of water hammer events. This assessment, which will include an impact /value appraisal, will consider all types of water hamers which are found to be significant to safety under Task 4.0.
Task 4 Water Hamer Safety Studies The basic objective of this task is to obtain information and develop analytical methods and calculations regarding water hamer which will be used in completing the revisions of CP and OL review procedures under Task 2.0 and in implementing the long-term position paper of Task 3.0.
The results of this task will also be used in implementing the revised CP and OL procedures developed under Task 2.0 and in the evaluation of water hammer incidents at operating reactors. The major part of the work will be done under technical assistance contracts.
Task 4.1 Review and Evaluation of Potential Water Hamer Problems This task, which will be completed under a technical assistance contract, will involve the review and evaluation of those actual and potential water hamer problems considered to be significant in 1700 304 A-1/3
Task A-1 Rev. No. 1 May 1978 the Task 1.1 report. The first objective is to identify typical scenarios (e.g., basic initiating mechanisms, design features, operating procedures, anticipated transients, and single failures) that could result in water hamer events. The safety significance of the water hamer events will then be assessed in terms of probability of occurrence and consequences. Where necessary, recomendations will be made on possible design or procedural changes to prevent the occurrence or minimize the consequences of the postulated water hamer.
Recomendations will also be made on criteria to be used in the licensing process. The second objective is to evaluate design features, operating procedures and systems (e.g., BWR jockey pump system) which are used to prevent the occur-rence of water hamer and to make recommendations on criteria to be used in the licensing process. This task will not be concerned with new PWR steam generators which are treated separately in Task 4.3.
The interim and final reports on this task will be distributed to responsible branches for consideration in completion of Tasks 2.0 and 3.0.
Task 4.2 Development of Current Information on Water Hamer The objectives of this task are (l') to provide a state-of-the-art review of experimental and analytical work reported in domestic and foreign literature which is pertinent to water hamer problems in nuclear plants, (2) to monitor Licensee Event Reports and experi-mental work on LOCA and ECC injection for information pertinent to water hammer, and (3) to ensure that information pertinent to water hamer which is obtained from licensees, vendors and architect-engineers under Task 3.0 and given in applicant responses to ques-tions raised during current CP and OL reviews will be brought to the attention of all responsibic branches in DOR and DSS. The state-of-the-art review will be accomplished under a technical assistance contract.
In support of the review, the Office of International Programs will be requested to obtain information from foreign sources on analyses and tests pertinent to water hamer in nuclear plants.
Interim and final reports on the review will be sent to responsible branches.
Information from the monitoring functions will be distributed when received via memoranda to respon-sible branches. The information obtained from the licensees and applicants will be maintained in control files for use by all responsible branches.
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Task A-1 Rev. No. 1 May 1978 Task 4.3 Water Hammer in PWR Steam Generators A.
Current Ste&m Generator Designs A number of damaging water hammer events have occurred which involve current steam generator designs with feedwater rings located near the top of the tube bundle and auxiliary feedwater lines connected to the sain feedwater lines. A report (NUREG-0291) has been completed under a technical assistance contract in FY 1977 which deals with this water hamer problem.
B.
New Steam Geneistor Designs Some new steam generator designs incorporate bottom feed and preheater boxes.
Recent tests have indicated that these designs siay be susceptible to water hamer resulting from rapid steam condensation when cold auxiliary feedwater is added to the preheater.
Potential water hammer problems for all new designs will be evaluated under this task. The major portion of the work will be done under a technical assistance program managed by the Auxiliary Systems Branch. Work during FY 1978 will cover review of scaling relationships presently available and the applicability of 1/8-scale test data in predicting results for full-scale steam generators. The FY 1979 work will involve review and evaluation of vendor design changes intended to prevent water hammer and consider-ation of other possible design changes and operating procedures for preventing water hammer. The results of this task will be used in defining an NRC position on new PWR steam generator designs under Task 2.0.
Task 4.4 Water Hamer Calculations There is a currently funded contract at Lawrence Livermore Laboratory, managed by the Engineering Branch, which is concerned with calcula-tions of pressure transients and stresses in PWR feedwater lines, using forcing functions assumed to represent those resulting from rapid condensation in the steam generator feedring. A final report on this work is scheduled for the end of FY 1977.
For FY 1978 a new technical assistance program is scheduled. A major objective of the new program is to provide analytical methods and calculations to be used in the evaluation of water hamer incidents at operating reactors. Flow closure functions representing the various initiating events will be formulated.
Existing computer programs will then be used to establish the system loading due to water hamer from various initiating events and to establish the 1700 306 A-1/5
Task A-1 Rev. No. 1 May 1978 sensitivity of these loads to system design parameters and operating procedures. The structural response to the water hammer will be calculated.
3.
Basis for Continued Plant Operation and Licensing Pendino Completion of Task Although water hammer can occur in any LWR and about one hundred incidents have been reported in 400 reactor years of operation, none have resulted in the off-site release of radioactivity. The systems most frequently affected are the feedwater systems of PWRs. A few incidents have caused pipe failure, but none in a reactor coolant pressure boundary. Adequate prctection from potential loss-of-coolant accidents, such as might be initiated by a water hammer event, is provided in plants by the emergency core cooling system. Since the probability of failure due to a water hammer is low and the conse-quences of postulated water hammer induced accidents would be ade-quately limited by currently installed redundant engineered safety features, continued operation and licensing of plants can proceed with reasonable assurance that the health and safety of the public is protected while this task is being conducted.
In the inte' rim, means to prevent water hammer in feedwater systems in PWRs are being instituted.
Applicants with new steam generator designs are being required to demonstrate that water hammer will not occur in these designs. Therefore for construction permits, there is reasonable assurance that such'a demonstration will be made prior to operation. Applicants with designs in which water hammer has been observed are being required to r.ake appropriate modifications. Thus plants with top feed steam generators are required to modify the feed-ring and test the system to assure water hammer will not occur.
Prior to start-up, tests to demonstrate that water hammer will not occur while entering the hot shutdown mode are being required.
Licensees of operating plants with steam generators having an internal feed-ring have been requested to evaluate the potential for water hammer in their feedwater systems and to make appropriate modifications
_., to assure that water hammer will not occu.*.
These modifica-tions will provide additional assurance that continued operation will not f..
present an undue risk to the health and safety of the public.
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Task A-1 Rev. No. 1 May 1978 4.
NRR TECHNICAL ORGANIZATIONS INVOLVED A.
Reactor Systems Branch, Division of Systems Safety, has lead responsibility for Tasks 1.0, 2.0 and 4.0 and has responsi-bility for subtasks 4.1 and 4.2.
In Task 2.0, Revision of CP and OL Review Procedures, RSS har responsibility for (1) revising sections of SF and SRP for which it has primary review responsibility, and (2) preparing, if required, branch positions, requests for changes in the Standard Technical Specifications and requests for preparation or modification of regulatory guides pertinent to these sections.
Manpower Estimates: 0.05 man year FY 1977; 0.8 man year FY 1978; 0.4 man year FY 1979; 1.25 man years Total B.
Auxiliary Systems Branch, Division of Systems Safety, has responsibility for Task 4.3.
In Task 2.0, Revision of CP and OL Review Procedures, ASB has responsibility for (1) revising sections of SF and SRP for which it has primary review responsibility, and (2) preparing, if required, branch positions, requests for changes in the Standard Technical Specifications, and requests for prepara-tion or modification of regulatory guides pertinent to these sections.
Manpower Estimates: 0.1 man year FY 1977; 1.0 man year FY 1978; 0.3 man year FY 1979; 1.4 man years Total C.
Containment Systems Branch, Division of Systems Safety.
In Task 2.0, Revision of CP and OL Review Procedures, CSB has responsibility for (1) revising sections of SF and SRP for which it has primary review responsibility, and (2) preparing, if required, branch positions, requests for changes in the Standard Technical Specifications, and requests for preparation or modification of regulatory guides pertinent to these sections.
Manpower Estimates:
man years FY 1977; 0.1 man year FY 1978; man years FY 1979; 0.1 asn-year Total 1700 308 A-1/7
Task A-1 Rev. No. 1 May 1978 D.
Mechanical Engineering Branch, Division of Systems Safety.
In Task 2.0, Revision of CP and OL Review Procedures, MEB has responsibility for (1) revisi a sections of SF and SRP for which it has primary review responsibility, and (2) preparing, if required, branch positions, requests for changes in the Standard Technical Specifications, and requests for prepara-tion or modification of regulatory guides pertinent to these sections.
man-1977; 0.2 san year FY 1978; Hanpower Estimates: F I san years FY year FY 1979; 0.3 man year Total E.
Plant Systems Branch, Division of Operating Reactors, has lead responsibility for Task 3.0, has responsibility for Task 4.4, has lead responsibility for collection of operating experience and for the maintaining of files on information from licensees under Task 4.2.
Manpower Estimates:
0.1 man year FY 1977; 0.5 man year FY 1978; 0.5 man year FY 1979; 1.1 man years Total F.
Engineering Branch, Division o'f Operating Reactors, has responsibility for evaluation and guidance of piping and structural response methods and calculations of Task 4.4, and has responsibility for assisti,3 in preparation of positions developed in Tasks 3.1 and 3.2.
Manpower Estimates:
0.05 man year FY 1977; 0.2 m:in year FY 1978; 0.3 c;a year FY 1979; 0.55 min year Total t
5.
TECHNICAL ASSISTANCE A.
Contractor To Be Selected (1)
Title:
Study of Fluid Flow Instabilities ia PWR Steam Generators (2) Responsible Division / Branch: Division of 5/ stems Safety, Auxiliary Systems Branch (3) Scope: This activity will provide technical assistance in the Task 4.3 work on evaluating water hammer problems for new PWR steam generator design. The work will involve review and evaluation of scaling relationships, 1/8-scale tests, proposed design changes to prevent water harner and consideration of alternative approaches to prevent water hammer.
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Task A-1 Rev. No. 1 May 1978 (4) Funding:
$10K FY 1977; $50K FY 1978; $50K FY 1979;
$110K Total B.
Contractor To Be Selected (1)
Title:
- Evaluation of Water Hammer Problem in Nuclear Power Systems (2) Responsible Division / Branch: Division of Systems Safety, Reactor Systems Branch (3) Scope: This is a program under Task 4.1 to define scenarios resulting in water hammer in various plant systems, evaluate the safety significance and where necessary recomend possible changes to prevent the occurrence and/or minimize the consequences of the water hammer. A contract requisition and detailed work plan will be prepared under Task 4.1.
(4) Funding: $70K FY 1978; $70K Total C.
Contractor To Be Selected (1)
Title:
State-of-the-Art Review of Experimental and Analytical Work Pertinent to Water Hammer in Nuclear Plant Systems (2) Responsible Division / Branch: Division of Systems Safety, Reactor Systems Branch (3) Scope:
Experimental and analytical work in the domestic and foreign literature will be reviewed for information pertinent to water hammer in nuclear plant systems. A contractor requisition and detailed work plan will be prepared under Task 4.2.
(4) Funding: $35K FY 1978; $35K Total D.
Lawrence Livermore Laboratory (1)
Title:
Effect of Hydraulic Shock on Water Hammer (2) Responsible Division / Branch: Division of Operating Reactors, Engineering Branch (3) Scope: This currently funded project under Task 4.4 will utilize existing structural dynamic computer programs to 1700 310 A-1/9
Task A-1 Rev. No. 1 May 1978 calculate the stresses from which one can determine the integrity of piping elements, supports and the operability
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of mechanical components. The project, which will be completed in September 1977, involves the following four tasks:
Task 1 - Characterization of shock waves in terms of parameters that are determined to be important in affecting the pipe integrity and component operability.
Task 2 - Development of a piping system model and the calculation of loads on components due to shock waves or water hammer.
Task 3 - Development of three-dimensional finite elements.
models for pipe bends, elbows, pumps, valves and supports and the calculation of stresses, strains and deformations.
If necessary, material and geometrical nonlinearities will be incor-porated.
Task 4 - Definition of component operability in terms of component strain or deformation during and following the transient. This task will be limited to pumps and valves only.
(4) Fundina: $75K FY 1977; $75K Total E.
Contractor To Be Selected (1)
Title:
Water Hamer Calculations (2) Responsible Division / Branch: Division of Operating Reactors, Plant Systems Branch (3) Scope: This project, which is part of the Task 4.4 effort, is concerned with the hydrodynamic / structural interactions in systems subject to water hamer loads. A major objective is to provide analytical methods and calculations to be used in the evaluation of water hamer incidents at operating reactors. The effort will involve numerical studies to establish the sensitivity of the structural consequences to the parameters of the initi-ating water hamer. The object is to provide a range of system design and/or operating procedures within which operating reactors may be judged to meet the intent of 1700.311 A-1/10
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Task A-1 Rev. No. 1 May 1978 future NRC guidelines on water hamer. A contractor requisition and detailed work plan will be prepared under Task 4.4.
(4) Fundina: $85K FY 1978; $85K Total 6.
INTERACTION WITH OUTSIDE ORGANIZATIONS Individual licensees, vendors and architect-engineers may be asked to supply information concerning plant-specific design features, operating procedures pertinent to water hamer. This task is closely related to one of the generic items identified by the ACRS and, accordingly, will be coordinated with the Committee as the task progresses.
7.
ASSISTANCE REQUIREMENTS FROM OTHER NRC OFFICES A.
Office of International Programs The Office of International Programs will be requested to obtain information on foreign programs or specific tests dealing with water hamer in nuclear plants.
B.
Office of Standards Development, Division of Engineering Standards On the basis of the work done under Task 2.0, it is expected that some requests will be made to the Division of Engineering Standards for modification and/or preparation of regulatory guides.
C.
Office of Nuclear Regulatory Research, Division of Reactor Safety Research There are no programs currently funded under the Division of Raactor Safety Research which are concerned specifically with water hamer problems. However, work sponsored by RSR (e.g.,
LOCA and ECC injection tests) will be monitored for information p rtinent to water hammer.
In addition, ree'!ests for research on water hamer say be made as the result of work on Tasks 2.0, 3.0 and 4.0.
8.
POTENTIAL PROBLEMS A.
The DOR / DSS Technical Review Group Report under Task 1.1 is input to Tasks 2.0, 3.0 and 4.0.
Extensive revision to the current draft is needed and two more stages of review and approval have been previously scheduled.
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Task A-1 Rev. No. 1 May 1978 B.
There is a general problem of achieving systematic and consist-ent treatment in the revisions to the SF and SRP under Task 2.0 8
and the preparation of positions under Task 3.0.
This arisas because of (1) the large number of systems involved, (2) the fact that some components and potential water hammer probless are the same for systems under different branches, and (3) the differerst approaches of individual branches. The water hammer problem should be censidered by branches under the three Assistant Directors in the Division of Systems Safety and by two branches under the Assistant Director for Operational Technology in the Division of Operating Reactors.
The inter-divisional DOR / DSS Technical Review Group was set up to achieve systematic coverage of water hammer. However, under this task plan, this group will be involved only in completion of the Task 1.1 report. This task plan is set up to achieve major objectives using normal line-management. The key to successful, task completion is (1) coordination of work objectives and personnel assignments at the A/D level prior to and after the initiation of branch efforts, (2) several stages of coordinated review within each division, and (3) provisions for inter-divisional comments and concurrence at the A/D level.
TheharlydevelopmentofanNRCpositiononwaterhammerin C.
steam generators is of major importance.
D.
Completion of the staff position on new steam generator designs in time to meet the Task 2.0 completion date of 04/30/79 is dependent upon the submission of test results from the vendors.
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ENCLOSURE 2 FY 1979 PROGRAM BRIEF PROGRAM: GRSR TITLE: PREPARATION OF DOCUMENTS FOR TAP A-1 CONT: FIN NO: A6279-9 CONTRACTOR: EG&G SITE:
INEL STATE: IDAHO TECHNICAL MONITOR:
C. W. BURGER PRINCIPAL INVESTIGATOR:
C. F. OBENCHAIN OBJECTIVE: TO COMPLETE THE REQUIRED DOCUMENTATION FOR TAP A-1 TASKS 1. 2, 2.0, AND 3.2.
BUDGET ACTIVITY: 60191006 OBLIGATION: $146K FY 1979 SCOPE DESCRIPTION:
THE PREPARATION OF THE REQUIRED DOCUMENTS FOR COMPLETION OF AS'FOLLOWS:
1.0 DEVELOP A NUREG
SUMMARY
REPORT TO SUtEARIZE NRC EFFORTS AN FUNDED TECHNICAL WORK ON WATER HAMER.
1.1 SUMMARIZE ACTUAL WATER HAMMER OCCURRENCES AND RELATE THE INITIATING MECHANISMS.
1.2 IDENTIFY WATER HAMPIR ANALYSIS CAPABILITIES AND DEFICIENC INCLUDE RESULTS OF THE STATE-OF-THE-ART LITERATURE RE 1.3 WHETHER ANALYSIS TECHNIQUES EXIST FOR FILLIhG ANALYSIS IDENTIFY ANY AVAILABLE EXPERIMENTAL DATA WHERE THE P 1.4 FOR PROVIDING INSIGHT TO SPECIFIC WATER HA MER PROBLEMS 1700 314
7 I 1.5 THIS REPORT WILL CONSIST ENTIRELY OF SulEARIZING INFORMATION A DOCUMENTED, THEREFORE NO ADDITIONAL ANALYSIS OR RESEARCH WILL BE PERFORMED.
1.6 EFFORTS FOR WHICH DOCUMENTATION IS OR WILL BE AVAILABLE AND WH SHOULD BE INCLUDED IN THE SUBJECT REPORT ARE AS FOLLOWS:
- NRC STAFF REPORT ON WATER HAMPIR IN NUCLEAR POWER PLANTS.
- CHECK VALVE CLOSURE.
- STEAM BUBBLE COLLAPSE.
- SLUG FLOW IN A VOIDED LINE.
- LITERATURE REVIEW.
- REVIEW AND EVALUATION OF ACTUAL AND POTENTIAL WATER HAPHER.
1.7 THE DRAFT
SUMMARY
REPORT SHALL BE COMPLETED BY AUGUST 1,1979.
2.0 PREPARE THE DOCUMENTATION REQUIRED TO SATISFY TASK 2.0 0F TA 2.1 Tl!E FOLLOWING SECTIONS OF THE SRP WILL BE CONSIDERED FOR PO CHANGES:
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3.9.1, 3.9.2, 3.9.3 5.2.2, 5.4.6, 5.4.7. 5.4.8 6.2.2, 6.3 9.2.1, 9.2.2, 9.3.4 10.3, 10.4.7, 10.4.9 15.3.3 MODIFY IF APPROPRIATE THE SIXTEEN (16) NOTED SECTIONS 2.2 THE STANDARD FORMAT TO INSURE THAT THE EFFECTS OF PO WATER HA!HER EVENTS ON NUCLEAR PIPING SYSTEMS ARE SAFETY REVIEWS.
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2.3 RECOMMEND, WHERE APPROPRIATE THE NEED FOR BRANCH TECHNICAL POSITI PREPARE THE BRANCH TECHNICAL POSITIONS WHERE THE RESPOLS 2.4 BRANCHES AGREE WITH THE NEED.
RECOMEND, WHERE APPROPRIATE THE NEED FOR PREPARATION OR MODIFICAT 2.5 OF REGULATORY GUIDES AND CHANGES TO THE STANDARD TE 2.6 DRAFTS OF ALL APPROPRIATE DOCUMENTATION SHALL BE COMPLE FEBRUARY 1, 1980.
3.0 DEVELOP AN NRC LONG-TERM POSITION.
3.1 FOLLOWING COMPLETION OF TASKS 2.0, 4.1, 4.2, AND 4.4, ASSESS THE NEED FOR ANY FURTHER REQUIREMENTS TO BE IMPOSED ON OPERATIN OTHER TYPES OF WATER HAMMER EVENTS.
THE ASSESSMENT WILL INCLUDE AN IMPACT /VN.UE APPRAISA 3.2 ALL TYPES OF WATER HAMMER WHICH ARE FOUND TO BE SIGN UNDER TASK 4.0.
PREPARE A LETTER BASED ON THE RESULTS OF THE ASSESSM 3.3 ANY ADDITIONAL WATER HAMMER PROBLEMS AND INCLUDE REC FOR ANY FURTHER REQUIREMENTS FOR OPERATING PLANTS.
COMPLETE THE DRAFT LONG-TERM POSITION BY APRIL 1, 1980.
3.4 4.0 DEVELOP A FINAL
SUMMARY
REPORT FOR TAP A-1.
4.1 INCLUDE AN INTRODUCTION.
4.2 STATE THE GOALS OF TASKS 1, 2, 3, and 4.
INCLUDE A SUM 4ARY OF EACH CHANGE MADE TO CURRENT 4.3 ANY ADDITIONAL RESEARCH WHICH MAY BE REQUIRED.
4.4 IDENTIFY 1700 316
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4.5 REFERENCE ALL DOCUMENTS PRODUCED UNDER TAP A-1 AND IDENTIFY ANY RECOMENDATIONS MADE FOR REGULATORY GUIDES OR CHANGES TO THE STANDARD TECHNICAL SPECIFICATIONS.
5.0 FOLLOW UP EFFORT FOR TASK 2.0.
5.1 DURING THE NRR DOCUMENT REVIEW PROCESS ADDITIONAL SUPPORT WILL BE REQUIRED. PENDING IDENTIFICATION OF SUCH SUPPORT BY RSR. THE CONTRACTOR SHOULD BE PREPARED TO HAVE STAFF AVAILABLE TO SUPPLY THE REQUIRED MANPOWER. RSR WILL RENEGOTIATE IF ADDITIONAL FUNDING IS REQUIRED.
6.0 ESTABLISH.A REPORTING SYSTEM TO COMPLY WITH THE WHITE BOOK REPORTING REQUIREMENTS.
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