ML17037C470

Letter Regarding Guidance for Proposed License Amendments Relating to Refuelings and an Enclosed List of Information Needed to Forecast Requirements for Reviews of Proposed License Amendments Relating to Refueling

ML17037C470
Person / Time
Site:	Nine Mile Point
Issue date:	06/18/1975
From:	Goller K Office of Nuclear Reactor Regulation
To:	Rhode G Niagara Mohawk Power Corp
References
Download: ML17037C470 (28)

Text

r DXSTRZBUTXON; NRC PDR HVanderhfolen 8 (975 Loc 1 PDR AG iambus so ORB¹3 Rdg FSchroeder Docket RSBoyd Docket No. 50-220 KRGoller RCDeYoung TJCarter Vhfoore GLear RDenise DJaffe TAbernathy SATeets CJDeBevec OELD 016E (3)

ACRS (143 Gray file PCheck Gentlemen: BSchemel DRoss It is a continuing objective of the Nuclear Regulatory Commission (NRC) to provide complete, prompt reviews of all applications for construction permits, operating 1icenses and license amendments. The length of time necessary to act upon such applications is, to a large extent, a function of the completeness of the information supplied by the licensee in support of its application. Completeness is particularly important for proposed license amendments that relate to reactor refuelings since they often include a wide range of proposed technical specification changes that must be developed and approved before the facility can return to operation. The tiRC has developed preliminary guidance (Enclosure 1) for use in preparing proposed license amendments that relate to refuelings that may help to assure that your submittals will 'include all required information.

Another related problem is that of lateness of licensee submittals which make it difficult and sometimes impossible for the staff to complete its review in time to accommodate scheduled dates for resumption of operation.

This problem becomes particularly difficult for license amendments that relate to refuelings that involve an extensive number of"technical specification changes. Moreover, the growing number of operating facilities requesting such license amendments is taxing the staff's ability to accommodate individual schedules, unless the requests are submitted with adequate time for review.

In order tq improve the efficacy and scheduling of our reviews of proposed license amendments that relate to refuelings we have prepared a list of the information that, we need to forecast the requirements for such reviews, (Refueling Information Request, Enclosure 2). Please submit this information for your Nine Nile Point Unit 1 facility within 30 days of receipt of this letter and update this information annually thereafter, or more often if appropriate.

We'uggest that this information be made a regular part of your annual operating reports OPPIC2 ~ QRBI..3~.......QRBB3....,..... D.'AD/DRY SVIINAML'W .,DJB.f5'.... .CJDeRevec ...........GLear&4.--'..KRGo11er-OATS ~ .,6I,...IL....,/73,. .6/............/7S....6/...)......../.2S.... -.S/.--l.E---/.7S-- .

Pons hEC.318 (Rcv. 9.53) hECM 0240 N U, 0'OOVSRNMSNT PRINTINO OPIIICEI 1074 020 100

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Niagara 1fohawk Power Corporation 2 JUN 1 8 1975 It is 'our hope that with this information we can assess your plans for refueling and schedule submittal dates which realistically reflect our review requirements and your need for timely, licensing action.

This request for generic information was approved by GAO under a blanket clearance number B-180225 (R0072); this clearance expires July 31, 1977.

Sincerely, (s/

Karl R. Goller, Assistant Director for Operating Reactors Division of Reactor Licensing

Enclosures:

1. Guidance for Proposed License Amendments Relating to Refueling

2. Refueling Information Request cc: w/encls See next page OERICE~

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Form hKC-318 (Rcv. 9.33) hECM 0240 4 U. OI OOVERNMENT PRINTINO ORPICEI IOT4 520 IOe

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Niagara Mohawk Power Corporation JUNI 8 875 l ~ ~

CC:

Arvin E. Upton, Esquire

'LeBoeuf, Lamb, Leiby g MacRae 1757 N Street, N. W.

Washington, D. C. 20036 Anthony Z. Roisman, Esquire Berlin, Roisman 5 Kessler 1712 N Street, N. W.

Washington, D. C. 20036 Dr. William Seymour, Staff Coordinator New York State Atomic Energy Council New York State Department of Commerce 112 State Street Albany, New York 12207 City Library 'swego 120 E. Second Street Oswego,. New York 13126

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ENCLOSURE 1 GUIDANCE FOR PROPOSED LICENSE AMENDMENTS RELATING TO REFUELING A. INTRODUCTION The refueling of a power reactor represents a change 'in the facility which may involve a change in the technical specifications or an unreviewed safety question. Title 10, CFR Part 50, Section 50.59(a) permits a licensee to make changes in the facility as described in the SAR, changes in the procedures as described in the SAR and conduct tests or experiments not described in the SAR without prior Commission approval unless such changes involve a change in the'technical speci-fications or involve an unreviewed safety question. The request for NRC authorization for any such change must include an appropriate safety analysis report (SAR). The format and content of such a SAR is the subject of this guide.

B. DISCUSSION The licensee must demonstrate that safe operation will continue with the new core. Generally, a refueling will involve only changes in the core loading. Any changes in facility design not associated with the refueling (reload) design and its effect on subsequent operation should be addressed by a separate document. Significant changes in fuel design or reactor control procedures may be addressed by reference to topical reports.

Two operating cycles or "loads" are of interest in a reload submittal. The "reload cycle" is the upcoming cycle, whose safety is to be evaluated. The "reference cycle" is the cycle to which the proposed

reload is to be compared. The appropriate reference cycle is therefore the cycle which has the most up-to-date, inclusive safety analysis report approved by the Commission. In most cases, this will be the "present", currently operating cycle. However, an applicant may use any cycle or, analysis back to the FSAR cycle for reference, if this analysis bounds the parameters of the proposed reload and uses currently approved analytical methods. The various safety analyses may be expedited by such reference if the reload cycle parameter values are bounded by the reference cycle values.

4 t The amount of detailed analysis required in any submittal depends on the type of reload. For equilibrium cycle reloads, where mechanical design and enrichment do not change it is expected that accident parameters will remain within their previously analyzed ranges and a reanalysis may not be required. Conversely, for non-equilibrium cycle reloads, the thermal and nuclear characteristics generally require new analysis and a full evaluation. 1&en a reload involves different analytical methods or design concepts, a complete review of these changes and their effects is necessary.

C. REGULATORY POSITION 5

Changes in design, analysis techniques, and other information relevant to a reload are often generic in nature. Generic information may be provided by reference to generic report rather than giving explicit justification in a reload SAR for a specific plant.

A reload submittal should be submitted at least 90 days before the planned startup date. If significant different analytical methods or design concepts are to be incorporated into the reload core and have not justified by generic review or if the changes otherwise entail a 'een significant hazards consideration, a significantly greater time period may be required. In cases where timing is a problem, there may be cases in which the submittal may be provided in sections so that the staff review can be expedited. The submittal should contain the following:

l. Introduction and Summar Give the purposes of the submittal and summarize the contents of the submittal.

2. 0 eratin History Discuss any operating anomalies in the current cycle which may affect the fuel characteristics in the 'reload cycle. It is recognized that only information from the first part of the cycle will be available.

3. General Descri tion Provide a core loading map for the planned reload core, showing the position, by zone, of new and irradiated fuel. Include the position of any te.t assemblies. Show the initial enrichment distribution of the fresh fuel, the initial burnup distribution, and the burnable poison distribution and concentration (if any). Deviations from this planned map at actual reload time are acceptable provided the finalized reload core's safety parameters are bounded by the safety analysis.

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4. Fuel S stem Desi n 4.

The reload fuel submittal should provide a table that presents the following items for both the proposed and the reference(cycle fuel:,,

fuel assembly type, planned number of reload and residual assemblies in the core, initial fuel enrichment, initial fuel density,,initial fill gas pressure, region burnups at BOG, and clad collapse time. For the new core loading in PWRs, the limiting region or fuel assemblies based on fuel performance considerations should be identified.

4.2 Mechanical Desi n Hhere fuel assemblies are considered new in concept, the following information should be provided, by reference or cxpli'.citly, for the reload fuel assemblies:

The vibration, flow and structural characteristics including seismic response should be presented. The dimensions and configur ation of fuel assembly components should be presented in tables and drawings. Particular attention should be given to the following items:

(1) For PHRs, control rod assembly accommodation and associated operational functions (for example, damping and travel limits).

(2) Fuel cladding mechanical interaction.

(3) Fuel rod bowing as related to fuel rod axial position and spacer grid flexibility.

(4) Steady-state fuel assembly hold-do'wn and lift-'off forces.

(5) Verification techniques for location and orientation of fuel assemblies in the core.

(6) Specific dimensional or material changes from present approved assemblies.

(7) Design of spacer grids as related to local flow effects, DNB considerations, and mechanical strength and integrity of the assembly.

Demonstrate by calculation with approved methods or tests that the new fuel design satisfies such design limits as stress intensity, strain, deflection, collapse, fretting wear and fatigue for all conditions, steady-state, normal, and abnormal transients. Any changes in design limits should be identified and )ustified.

Demonstrate by calculation with approved methods or tests that the new fuel design meets the requirements of Appendix K of 10 CFR 50.

4.3 Thermal Desi n Where fuel assemblies are considered new in concept, fuel thermal performance calculations based on the above mechanical design and the vendor s approved fuel performance model should be provided. Fuel cladding integrity and collapse considerations should be included. This may be accomplished by suitable reference.

4.4 Chemical Desi n Where fuel assemblies are consider ed nqw in concept or utilize component I

materials that differ from the present design, chemical compatibility of all possible fuel-cladding-coolant-assembly interactions should be analyzed.

This may be accomplished by suitable reference.

4.5 0 eratin Ex erience Previous operating experience as related to safety considerations with comparable fuel rod/assembly designs should be presented. This may be accomplished by suitable reference.

5. NUCLEAR DESIGN 5.1 Ph sics Characteristics Provide information regarding any changes from the reference cycle to the reload cycle for the following parameters used in the safety analysis:

For BOC, EOC, and any extremum during the cycle:

(1) Moderator Coefficients (e.g., temperature, pressure, density, or void. Give or refer ence the power distributions used in their development.)

(2) Doppler Coefficxent (3) Maximum Radial and Axial (or Total) Peaking Factors (4) Egected Rod Worth (for PWRs)

(5) Rod Drop Parameters (for BWRs)'or BOC and EOC:

(1) Delayed Neutron Fraction (2) Critical Boron Concentration (for PWRs)

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7 (3) Boron North (for PNRs)

(4) Standby Liquid Control System 11(orth (for BNRs)

(5) Scram Function (for BNRs)

For PWRs, provide, in tabular form, a detailed calculation of the 1

shutdown margin for the BOC and EOC and any mid-cycle minimum of the reference and reload cycles. This table should also indicate the required margin. For BNRs, provide. the shutdown margin curve.

For PlNs, specify the control rod patterns to be used during the reload cycle, including any rod interchanges and any differences from the reference cycle.

5.2 Anal tical In ut Describe briefly the information gathered on the burnup history of the exposed fuel, and how it was used in the reload analysis only if required to support reload design changes. This may be done by reference. Indicate how the incore measurement calculation constants (or matrices) to be used in calculating bundle powers were prepared for the reload cycle. This may be done by reference.

5.3 Chan es in Nuclear Desi n Describe any changes in core design features, calculational methods, data or information relevant to determining important nuclear design parameters which depart from prior practice for this reactor, and list the affected parameters. This should be done by reference where possible.

Discuss in detail or give a reference describing any significant changes in operational procedure from the reference cycle with regard to axial power shape control, radial power shape control, xenon control, and tilt control.

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In cases where different analytical methods are used, detailed information I,

on the new analytical methods for evaluating core neutronic behavior should be supplied, and any interfacing between the new andI old methods should be I

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described. This should be done by reference where possible.

6. Thermal H draulic Desi n tI In the event there are changes in the fuel geometry, such as spacer grid design,"spacer grid axial separation, fuel pin spacing, or of the fuel pin or oontrol rod guide tube; or if there are changes in the radial or axial design power distributions of the core, evaluate the effects of these changes on:

(a) The minimum DNBR/CHFR/CPR values for normal operation and anticipated transients.

(b) The hydraulic stability of the primary coolant system for all conditions of steady-state operation, for all operational transients including load following maneuvers, and for partial loop operation.

This may be done by appropriate reference.

In cases where different calculational pr ocedures for thermal hydraulic design are used, these procedures and appropriate calculations should be described or referenced.

7. Accident and Transient Anal sis The potential effect of any changes in the xeload fuel design on each incident listed in the Accident and Transient Analysis section of the reference cycle analysis should be considered.

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e Provide a table of the input parameters applicable to all accidents and transients. This table of "common" parameters should list two columns for each parameter: the limiting values for the reference cycle and the limiting values for the reload cycle.

- A second table should be pr ovided which lists each accident with its accident-specific input'parameters. The table should also list limiting values for the reference cycle and the reload cycle.

In case an accident input parameter falls outside of bounds previously analyzed, provide or reference a re-analysis of the accident.

Justify any changes from the reference cycle in accident analysis techniques, calculational methods, correlations, and codes. If this is not done by reference to a topical report, an appropriately longer time period will be required for approval of the reload submittal.

8. Pro osed 14odifications to Technical S ecifications Present the proposed modifications to the Technical Specifications.

Justify the changes.

9; Startu Pro ram I

List, and briefly describe the planned startup tests associated with core performance. Recommended tests include:

For PMRs:

(1) Control Rod Drive Tests and Drop Time (Hot)

(2) Critical Boron Concentration

(3) Control Rod Group Worth (4) Egected Rod Worth (5) Dropped Rod Worth (6) Moderator Temperature Coefficient (7) Power Doppler Coefficient (8) Startup Power Maps For BWRs:

(1) Control Rod Drive Tests and Scram Time (Cold and Hot)

(2) Shutdown Margin With Host Reactive Rod Withdrawn (3) Patterns for Criticality

~. 4 ENCLOSURE 2 REFUELING INFOMfATION RE UEST

l. Name of facility

2. Scheduled date for next xefueling shutdown

3. Scheduled date for restart following xefueling

4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

If answer is yes, what, in general, will these be?

If answer is no, has the xeload fuel design and core configuration been reviewed by your Plant Safety'eview Committee to determine whether any unx'eviewed safety questions are associated with the core reload (Ref.

10 CFR Section 50.59)?

If no such review has taken place, when is it scheduled?

5. Scheduled date(s) for submitting pxoposed licensing action and supporting information

6. Important licensing considerations associated with refueling, e.g.,

new or different fuel design or supplier, unreviewed design or performanc'e analysis methods, significant changes in fuel design, new operating procedures.

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