ML20217F348

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Marked-up & Reprinted TS Pages,Changing TS Requirements for Insp of RCP Flywheels
ML20217F348
Person / Time
Site: Mcguire, Catawba, McGuire  Duke Energy icon.png
Issue date: 10/15/1999
From:
DUKE POWER CO.
To:
Shared Package
ML20217F345 List:
References
NUDOCS 9910200299
Download: ML20217F348 (28)


Text

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l Attachment la McGuire Units 1 and 2 Technical Specifications Marked copy I

f 9910200299 991015 PDR ADOCk 05000369 P

PDR

ProgrIms end Manuals 5.5 l

l 5.5 Programs and Manuals 5.5.5 Radioactive Effluent Controls Proaram (continued) li.

A determination that the change (s) maintain the overall j

conformance of the solidified waste product to existing requirements of Federal, State, or other applienble regulations or a determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302,40 CFR Part 190,10 CFR 50.36a, and Appendix 1 to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations; 2.

Shall become effective after approval of the station manager.

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Shall be submitted to the Commission in the form of a complete, legible copy of the entire Section 16.11 of the UFSAR as a part >f or concurrent with the Radioactive Effluent Release Report for the period of the report in which any changes to Section 16.11 of the UFSAR was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e.,

month / year) the change was implemented.

5.5.6 Component Cyclic or Transient Limit This program provides controls to track the UFSAR, Section 5.2.1.5, rFelic and transient occurrences to ensure that components are maintained withe the design limits.

5.5.7 Reactor Coolant Pumo Flywhee! Inspection Proaram This program shall provide for the inspection of each reactor coolant pump flywheel per the recommendations of Regulatory. Position c.4.b of Regulatory Guide 1.14, Revision 1, August 1975.

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(continued) lAcGuire Units 1 and 2 5.5-5 Amendment Nos.184/166

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l INSERT FOR TECHNICAL SPECIFICATIONS In lieu of Position C.4.b(1) and C.4.b (2 ), a qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle one-half of the outer radius or a surface examination (MT and/or PT) of exposed surfaces of the removed flywheels may be conducted at approximately 10 year intervals coinciding with the Inservice Inspection schedule as required by ASME Section XI.

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s Attachment Ib Catawba' Units 1 and 2 Technical Specifications Marked Copy i

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Programs and Manuals 5.5 l

5.5 Programs and Manuals I'

5.5.5 Radioactive Effluent Controls Procram (contirmed)

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Shall be documented and records of reviews performed shall be retained. This documentation shall contain:

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Sufficient information to support the change (s) together with the appropriate analyses or evaluations justifying the change (s), and

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A determination that the change (s) maintain the overall onnformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations or a determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302,40 CFR Part 190,10 CFR 50.36a, and Appendix l to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations; 1

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Shall become effective after approval of the station manager.

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Shall be submitted to the Commission in the form of a complete, legible copy of the entire Section 16.11 of the UFSAR as a part of or concurrent with the Radioactive Effluent Release Report for the period ol the report in which any changes to Section 16.11 of the UFSAR was made. Each change shall be identified by markings I

in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e.,

month / year) the change was implemented.

5.5.6 Component Cyclic or Transient Limit l

This program provides emtrols to track the UFSAR, Section 3.9.1.1, cyclic and transient occurrences to ensure that components are maintained within the design limits.

5.5.7

- Reactor Coolant Pump FivwheelInspection Proaram l

This program shall provide for the inspection of each reactor coolant pump flywheel per the recommendations of Regulatory. Position c.4.b of Regulatory Guido 1.14, Revision 1. August 1975.

L (continued) l Catawba Units 1 and 2 5.5-5 Amendment Nos. 173/165 L

s INSERT FOR TECHNICAL SPECIFICATIONS In lieu of Position C.4.b(1) and C. 4.b (2 ), a qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle one-half of the outer radius or a surface examination (;MT and/or PT) of exposed surfaces of the removed flywheels may be conducted at approximately 10 year intervals coinciding with-the Incervice Inspection schedule as required by ASME Section XI.

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1 e a McGuire Units 1 and 2 Technical Specifications Reprinted Pages Remove Page Insert Page 5.5-5 5.5-5 k

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i Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.5 Radioactive Effluent Controls Proaram (continued) ii.

A determination that the change (s) maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations or a determination that the change will maintain

' the level of radioactive effluent control required by 10 CFR 20.1302,40 CFR Part 190,10 CFR 50.36a, and Appendix l to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations; 2.

Shall become effective after approval of the station manager.

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Shall be submitted to the Commission in the form of a complete, legible copy of the entire Section 16.11 of the UFSAR as a part of or concurrent with the Radioactive Effluent Release Report for the

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period of the report in which any changes to Section 16.11 of the UFSAR was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shallindicate the date (i.e.,

month / year) the change was implemented.

5.5.6 Component Cyclic or Transient Limit This program provides controls to track the UFSAR, Section 5.2.1.5, cyclic and transient occurrences to ensure that components are maintained within the design limits.

5.5.7 Reactor Coolant Pumo Flywheel Inspection Proaram This program shall. provide for the inspection of each reactor coolant pump flywheel per the recommendations of Regulatory Position C.4.b of Regulatory l

Guide 1.14, Revision 1, August 1975.

l In lieu of Position C.4.b(1) and C.4.b(2), a qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle one-half of the outer radius or a surface examination (MT and/or PT) of exposed surfaces of the removed flywheels may be conducted at approxirsately 10 year intervals coinciding with the inservice Inspection schedule as required by ASME Section XI, (continued)

McGuire Units 1 and 2 5.5-5 Amendment Nos.

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' Catawba Units 1 and 2 Technical Specifications Reprinted Pages Remove Page Insert Page 5.5-5 5.5-5 J

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Programs and Manuals 5.5 5.5 Programs and Manuals l.

5.5.5 -

Radioactive Effluent Controls Proaram (continued) l 1.

Shall be documented and records of reviews performed shall be l

retained. This documentation shall contain:

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Sufficient information to support the change (s) together with the appropriate analyses or evaluations justifying the change (s), and ii.

A determination that the change (s) maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable -

regulations or a determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302,40 CFR Part 190,10 CFR 50.36a, and Appendix i to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations; 2.

Shall become effective after approval of the station manager.

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Shall be submitted to the Commission in the form of a complete, legible copy of the entire Section 16.11 of the UFSAR as a part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any changes to Section 16.11 of the j

l UFSAR was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e.,

month / year) the change was implemented.

5.5.6 Comoonent Cyclic or Transient Limit This program provides controls to track the UFSAR, Section 3.9.1.1, cyclic and

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transient occurrences to ensure that components are maintained within the design limits.

l 5.5.7 Reactor Coolant Pumo Fivwheel Insoection Proaram This program shall provide for the inspection of each reactor coolant pump flywheel per the re mmmendations of Regulatory Position C.4.b of Regulatory l

Guide 1.14, Revi. Jn 1, August 1975.

In lieu of Position C.4.b(1) and C.4.b(2), a qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle one-half of the outer radius or a surface examination (MT and/or PT) of exposed surfaces of the removed flywheels may be conducted at approximately 10 year intervals coinciding with the Inservice Inspection schedule as required by ASME Section XI.

(continued) l Catawba Units 1 and 2 5.5-5 Amendment Nos, t

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Description of Proposed Changes and Technical Justification

Background

General Design Criterion 4, Environmental and dynamic effects design bases contained in 10CFR50, Appendix A, General Design

. Criteria for Nuclear Power Plants requires that nuclear power plant structures, systems, and components important to safety be protected-against the effects of missiles that might result from equipment failures. NRC Regulatory Guide 1.14 describes a method acceptable to the NRC for implementing this requirement as.it applies to minimizing the potential for missile generation caused by failures of reactor coolant pump flywheels.

The McGuire and Catawba reactor coolant pumps are located in each Reactor Coolant System loop. The reactor coolant pumps provide the ability to circulate the reactor coolant fluid throughout-the primary syst,

The reactor coolant pumps are motor-driven, vertical-shatt, centrifugal pumps. The reactor coolant pump flywheel is located on the upper end of the motor rotor, above the upper radial guide bearing. The flywheels provide the reactor coolant pungs with an extended period of flow coastdown during accide.ue that involve.a loss of for.ced circulation. Accidents involving a loss / decrease in reactor coolant' flow are evaluated in Chapter 15 of the McGuire and Catawba Updated Final Safety Analysis "eports. The flywheels increase the combined pump / motor rotat anal-inertia, which' prolongs pump'coastdown to assure a more gradual loss of main coolant flow to the reactor core during some events that

- decrease Reactor Coolant-System flow rate.

These events are

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discussed.in McGuire and Catawba UFSAR Section 15.3, " Decrease in Reactor Coolant System Flow Rate."

The reactor coolant pumps, motors, and the associated flywheels for the McGuire, and Catawba units were manufactured by Westinghouse Electric Corporation. Therefore, the provisions of WCAP-14535A, Topical Report on Reactor Coolant Pump Flywheel Inspection Elimination, apply to all the flywheels on the Duke

. Energy Corporation McGuire and Catawba Units.

WCAP-14535A provides the primary technical justification for this LAR and was developed under the cognizance of the Westinghouse owners Group.

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4 Description of Proposed Changes and Technical Justification All the Duke reactor coolant pump flywheels are made of flame cut plates fabricated from vacuum degassed ASTM 533, Grade B, Class 1 steel. The initial design of the flywheel plate

. material confirmed suitability of this material for its intended use and consistency with the acceptance criteria spccified in NRC Regulatory Guide 1.14. This flywheel material meets the applicability requirercents of WCAP-14535A. The-integrity of the flywheels is ensured by the use of suitable material (as discussed above), correct design, and appropriate testing.and inspection programs. The design and quality assurance considerations are discussed in detail in the

. applicable sections of each station's UFSAR (Section 5.2.6/ Table 5-36 for McGuire and Section 5.4.1.5/ Table 5-24 for Catawba). Marked copies of these UFSAR sections are provided for each station in Attachments 6a and 6b. The flywheels are tested to a speed of 125% above the normal operating speed of the motor. The inservice inspection program for the flywheels is performed using approved plans and procedures and in accordance with applicable Technical Specifications.

Description of Proposed Changes The existing and proposed Technical Specifications for McGuire and Catawba Nuclear Stations are shown in the following paragraphs. The discussion for McGuire and Catawba is combined, since the existing and proposed Technical Specifications for these two stations are identical.

The existing McGuire and Catawba Technical Specification 5.5.7 reads:

"This program shall provide for the inspection of each reactor coolant pump flywheel per the recommendations of Regulatory Position c.4.b of Regulatory Guide 1.14, Revision 1, August 1975."

This LAR will change Technical Specification 5.5.7 to:

"This program shall provide for the inspection of each reactor, coolant pump flywheel per the recommendations of Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1, August 1975.

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Description of Proposed' Changes and Technical Justification LIn -lieu of Position C.4.b(1) and C.4.b (2), a qualified in-place UT examination over the volume from the inner bore of the flywheel-to the circle one-half of the outer radius or a surface-examination DCr and/or PT) of exposed j

surfaces of the removed flywheels may be conducted at approximate 1y'10 year intervals coinciding with the Inservice Inspection schedule as required by ASME Section XI."

, Regulatory position-C.4.b of Regulatory' Guide 1.14 addresses inservice inspection for reactor boolant pump flywheels and specifies that an inplace ultrasmu;: volumetric examination of the areas of higher stress concentration at the bore and keyway

-be performed at approximately 3-year intervals. Additionally, performance of a surface examination of all exposed surfaces and complete ultrasonic volumetric examination at approximately 10-year intervals are specified. The existing McGuire and Catawba Technical Specification 5.5.7 contains a direct reference to Regulatory Position C.4.b of Regulatory Guide 1.14.

For the future, in lieu of Positions C.4.b(1) and C.4.b(2) of Regulatory guide 1.14, implementation of the changes proposed by this LAR at McGuire, and Catawba _would require either: 1)

Conduct a qualified in-place ultrasonic examination over the volume from the inner bore of the flywheel to the circle of one

half the outer radius, or 2f Conduct a surface examination (magnetic ~ particle and/or penetrant _ testing) of exposed surfaces defined by the volume of the disassembled flywheels.

The examination-chosen from these two alternatives would be conducted on a frequency of once every ten years. These proposed changes are consistent with the conclusions reached in:WCAF 14535A.

Discussion l

.The changes proposed in this LAR will reduce the frequency and scopa of the existing reactor coolant pump flywheel inspection program. The proposed changes do not seek to completely eliminate the flywheel inspections as originally proposed in WD.P-14535. Reducing the frequency of inspections reduces costs and personnel radiation-exposure without impacting the safety of future _ plant operations.

Duke performed a detailed cost 3

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d Description of Proposed Changes and Technical Justification savings study and'the results indicated an estimated net cost savings of.more than $400,000 through the remainder of the 40-year life of McGuire and Catawba.

This LAR is categorized as a Cost Beneficial Licensing Action.

The proposed changes are consistent-with the-conclusions reached in WCAP-14535A, which was reviewed and approved by the NRC through the issuance of a

-safety evaluation dated September 12, 1996. In accordance with the requirements of this NRC safety evaluation, Duke Energy Corporation confirms that the flywheels installed at McGuire and_. Catawba Nuclear Stations are manufactured of ASTM 533, Grade B, Class 1 steel (previously discussed above) and that the additional requirements specified in the conclusions section of the NRC's safety evaluation are met by this LAR. The NRC safety evaluation required additional actions for plants having Group-10 and Group-15 flywheels. None of the flywheels on the reactor coolant pumps installed at McGuire or Catawba Nuclear Stations are in the Group-10 or Group-15 category.

WCAP-14535A contains the results of flywheel inspections from more than 50 nuclear power plants, covering more than 200 flywheels, and covering well over 700_ examinations. The results identified no indications that would cause the integrity of the

. flywheels to be-questioned.

McGuire and Catawba flywheel examinations are conducted in accordance with the Duke Energy

-Corporation Inservice Inspection Program during refueling outages or periods-of reactor coolant pump / motor maintenance.

To date, a total of 110 reactor coolant pump flywheel inservice inspection examinations have been performed at McGuire and Catawba Nuclear Stations. The number and type of examinations per. unit are shown below:

McGuire Unit 1: 24 Ultrasonic Examinations, 8 Magnetic Particle Examinations McGuire-Unit 2: 23 Ultrasonic Examinations, 8 Magnetic Particle Examinations

' Catawba Unit 1: 20 Ultrasonic Examinations, 4 Magnetic Particle Examinations Catawba Unit 2: 18 Ultrasonic Examinations, 5 Magnetic Particle Examinations 4

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Description of Proposed Changes and Technical Justification No recordable or reportable indications have been found.

Precedent NRC Licensino Actions The NRC has previously approved the changes contained in this LAR for implementation at other nuclear power plants. These plant-specific approvals include Turkey Point, Safety Evaluation dated February 11, 1997; D.

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Cook, Safety Evaluation dated August 8, 1997; and North Anna, Safety Evaluation dated April 22, 1998.

Additionally, Industry /TSTF Standard Technical Specification Change Traveler No. TSTF-237, Rev.1 (which applies to Standard Technical Specification 5.5.7) has been approved by the NRC.

The changes to the McGuire and Catawba Technical Specification 5.5.7 that are proposed in this LAR are consistent with TSTF-237, Rev.

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Conclusion The results of the studies documented in WCAP-14535A and the historical results of Duke's own inservice inspection program l

demonstrate that reducing the scope and frequency of flywheel inspections, as proposed in this LAR, will not negatively impact flywheel integrity or plant safety. In actualit y, the results of the flywheel inspections and conclusions discussed in WCAP-14535A show that flywheel integrity are increased by eliminating all inspections. This LAR will cause no change in the probability of failure for the flywheels, and thereby no increase in the probability of missile generation caused by a failed flywheel. Also, the ability of the flywheels to fulfill their contribution to the design basis reactor coolant flow coastdown function will be preserved. Therefore, the additional personnel exposure and other burden that would be incurred by the continuance of the current inspection program are not warranted. Finally, this LAR will implement changes that are consistent with a program that has been evaluated and approved on both generic and plant-specific bases by the NRC.

Based upon the discussion presented above, Duke Energy Corporation requests timely NRC review of this LAR and approval by February 1,

2000.

This approval date will allow the initial implementation of this LAR during the next Catawba Unit 2 refueling outage, currently scheduled to begin on March 4, t

2000.

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I No Significant Hazards Consideration Determination The following discussion is a summary of the evaluation of this LAR against the 10CFR50.92 (c) requirements to demonstrate that all three of the stated standards are satisfied. A no significant hazards consideration is indicated if operation of the facility in accordance with the changes proposed in this LAR would not:

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Involve a significant increase in the probability or consequences of an accident previously evaluated. or 2.

Create the possibility of a new or different kind of accident from any accident previously evaluated, or 3.

Involve a significant reduction in a margin of safety.

First Standard Would implementation of the changes proposed in this LAR involve a significant increase in the probability or consequences of an accident previously evaluated?

No. There are no accident probabilities or consequences impacted by this LAR. As discussed in Attachment 3, following a reduction in the scope and frequency of the examinations currently required by the applicable Technical Specifications and Regulatory Guide 1.14, an adequate inservice inspection program will continue to be maintained for the reactor coolant pump flywheels. Since the integrity of the flywheels will continue to be ensured, these components will contisae to be available to fulfill their existing design function during pump coastdown flow transients. Additionally, there is no more risk that the flywheels will become a source of missile generation. Consequently, there is no significant increase in the probability or consequences of an accident previously evaluated.

Second Standard Would implementation of the changes proposed in this LAR create the possibility of a new or different kind of accident from any previously evaluated?

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l No Significant Hazards Consideration Determination No. The proposed changes contained in this LAR only reduce the existing inspection requirements for the reactor coolant pump flywheels. This LAR proposes no changes to the plants' design, equipment, or method of operation at either McGuire or Catawba Nuclear Station. Furthermore, the reduction in the inspection requirements for the flywheels has been generically approved-by the UU: and is justified by WCAP-14535A. Therefore, since implementation of this LAR results in no actual impact upon either of the Duke nuclear plants, and since the integrity of the flywheels will continue to be ensured at an acceptable level, no new or different kinds of accidents are being created.

Third Standard q

Would implementation of the changea proposed in this LAR involve a significant reduction in a margin of safety?

No. Margin of safety is related to the confidence in the ability of the fission product barriers to perform their design functions during and following an accident situation.

These barriers include the fuel cladding, the reactor coolant system, and the containment system. These barriers are unaffected by the changes proposed in this LAR. As discussed in WCAP-14535A, a reduction in the frequency for performing the inservice inspections currently done in accordance with Regulatory guide 1.14 will not preclude the ability to accurately demonstrate the integrity of the reactor coolant pump flywheels. This LAR creates no additional threat to the integrity of the fission product barriers from the standpoint of missile generation or otherwise. Therefore, implementation of the changes proposed in this LAR does not impact the assumption of the integrity of the flywheels, the fission product barriers, or any other accident analyses assumptions.

Consequently, no margin of safety will be significantly impacted by this LAR.

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No.Significant Hazards Consideration Determination Conclusion Based ~upon the preceding evaluation, performed pursuant to 10CFR50.92,. Duke Energy Corporation has concluded that implementation of'this LAR at McGuire and Catawba Nuclear Stations will not involve a significant hazards i-consideration. The changes proposed in this LAR will-allow for a reduction in the inservice inspection requirements for the-reactor coolant pump flywheels as approved by the NRC and ju' tified by Topical Report WCAP-14535A. Following s

implementation of the proposed changes, Duke's inservice

-inspection programs will' continue to adequatel3 ensure the structural integrity of the flywheels.

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Environmental Assessment / Impact Statement Pursuant to 10CFR51.22 (b), an evaluation of this LAR has been performed to determine whether or not it meets the criteria:for categorical exclusion set out in 10CFR51. 22 (c) (9) of the regulations.

This LAR for the McGuire Units 1 and 2 and the Catawba Units 1 and 2 Technical Specifications proposes changes that reduce the current scope and frequency of inservice inspections performed on the reactor coolant pump flywheels. The proposed changes are based upon an industry study conducted by the Westinghouse Electric Corporation, under the cognizance of the Westinghouse Owners Group, and documented in Topical l

Report WCAP-14535A. This topical report has been approved on a generic basis by the NRC. Following implementation of the i

changes proposed in this LAR, the integrity of the flywheels l-will continue to be ensured in an acceptable manner.

l Consequently, implementation of this LAR at the McGuire and Catawba Nuclear Stations will have no adverse impact on: 1) the reactor coolant pump flywheels, 2) the reactor coolant

. systems, 3) the emergency core cooling systems or any other L

plant systems, or 4) a contribution to any additional

_ quantity or type of effluent being available for environmental impact or personnel exposure.

As applicable to LAR, it has been determined there are:

1) no significant hazards consideration (see Attachment 4);
2) no significant change in the types, or significant increase in the amounts of any effluents that may be released offsite; and

' 3) no significant increase in individual or cumulative occupational radiation exposures involved.

Therefore, this amendment to the McGuire and Catawba Technical Specifications meets the criteria of 10CFR

51. 22 (c)-(9) for categorical exclusion from the requirements for performing an environmental impact statement / assessment.

1 a McGuire Units 1 and 2 Updated Final Safety Analysis Report Pages 5-49 and 5-50 and Table 5-36 Marked Version 1

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McGuire Nuclear Station 5.2 Integrity of the Reactor Coolant Pressure Boundary I

Other "in process" weld inspections are performed (such as verification of welding procedare parameters, l

welder qualification, joint identification, etc.) in accordance with ASME Section III code requirements and additional requirements of the Duke Power Company, Construction Department Quality Assurance Procedures.

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Control of welding in the BWI steam generators is as follows:

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The requirements of Regulatory Guide 1.31 shall be imposed for welding of austenitic stainless steel. All 6

ASME Code welds performed between austenitic stainless steel and ferdtic steels or nickel-base alloys 6

shall be performed with ASME II, Part C SFA 5.14 ERNiCR-3 filler metal. Stainless steel filler material 6

used to join austenitic steel to itself shall conform to Regulatory Guide 1.31 with a delta fernte 6

requirement for the deposit of 6 5-15 FN. The maximum limit for carbon content in austenitic stainless 6

steel filler materialis 0.02%

5.2.6 PUMP FLYWHEEL The integrity of the reactor coolant pump flywheel is assumed on the basis of the following design and quality assurance procedures.

5.2.6.1 Design Basis 6

During normal operation, the reactor coolant pump flywheel possesses sufficient kinetic energy to produce 6

high energy missiles in the event of structural failure. Conditions which may result in overspeed of the 6

reactor coolant pump increase both the potential for failure and the kinetic energy of the flywheel.

6 Structuralintegrity of the flywheelis ensured by a range of actions as recommended by NRC Regulatory 6

Guide 1.1 include conservative stress -Inet insnections and tests. #

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e / ~ H e r M E " ' "* 5 5.2.6.2 Fabrication and Inspekdesc /defw/4 5'c No " 6' * * 3

  • I4'J' "#b.*'M The flywheel consists of two plates, approximately five inches and eight inches thick, bolted together. The flywheel material is produced by a process that mmimizes flaws in the material and improves its fracture toughness properties, such as vacuum-melting, or electroslag remelting. Each plate is fabricated from SA533, Grade B, Class I steel. Supplier certification reports are available for all plates and demonstrate the acceptability of the flywheel material on the basis of the requirements of AEC Regulatory Guide 1.14.

6 Flywheel blanks are flame-cut from the AS33 Grade B, Class 1 plates with at least 1/2 inch of stock left on the outer and bore radii for machining to fmal dimensions. The fmished machined bores are subjected to magnetic puticle or liquid penetrant exammations. The fmished flywheels are subjected to 100 percent vohtmetric ultrasonic inspection per Paragraphs NB 2532.1 and NB-2532.2 of the ASME Section Ill Boiler and Pressure Vessel Code.

5.2.6.3 Acceptance Criteria and Compliance with NRC Regulatory Guide 1.14 The reactor coolant pump motor fly wheel shall conform to the following material acceptance.

1. The Nil-Ductility Transition Temperature (NDTT) of the flywheel material shall be obtained by two (2) drop weight tests (DWT) which will exhibit "no break" performance at 20*F in accordance with ASTM E 208.. The above drop weight test demonstrate that the NDTT of the flywheel material is no higher than 10*F.

(15 FEB 1999) 5-49

5.2 Integrity of the Reactor Coolant Pressure Boundary McGuire Nuclear Station O

2. A mmunum of three (3) Charpy V-notch impact specimens shall be tested at ambient (70*F)

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temperature in accordance with the specification ASTM-E-23. The Charpy V notch (Cv) energy in J

both the parallel and normal orientation with respect to the rolling direction of the flywheel material shall be at least 50 ft-lbs at 70*F to demonstrate compliance with Regulatory Guide 1.14. A lower bound K1 reference curve (see Figure 5-17) has been constructed from dynamic fracture toughness data generated in SA533, Grade B, Class I steel. All data points are plotted on the temperature scale relative to the NDT temperature. The construction of the lower bound below which no single test point falls, combined with the use of dynamic data when flywheel loading is essentially static, together 6

represents a large degree of conservatism. Reference of this curve to the guaranteed Nil Ductility Transition Temperature of + 10'F indicates that, at the predicted flywheel operating temperature of Il0'F, the minimum fracture foughness is in excess of 100 KSI-int /2 This conforms to Regulatory Guide 1.14 requirements that the dynamic stress intensity factor must be at least 100 KSI-init2 Precautionary measures taken to preclude missile formation from primary coolant pump components, assure that the pumps do not produce missiles under any anticipated accident condition. Each component of the primary pump motors has been analyzed for missile generation. Any fragments of the motor rotor would be contained by the heavy stator. The same conclusion applies to the pump impeller because the small fragments that might be ejected would be contained by the heavy case.

1 The flywheels are tested to a speed of 125% above the normal operating speed of the motor but they 6

are not tested to the anticipated overspeed if a break occurs in the reactor coolant piping in either the suction or discharge side of the pump. However, the integrity of the flywheel under the worst overspeed condition during a piping break in the reactor coolant system is demonstrated by analysis and model testing. The ductile analysis is performed using the faulted condition criteria (Appendix B) of Section III of the ASME Boiler and Pressure Vessel Code. Compliance with the limits given in the code for the faulted condition assums that the flywheel can withstand the worst overspeed condition with sufficient margin.

Thus,it is concluded that flywheel plate materials are suitable for use and can meet Regulatory Guide 1.14 acceptance criteria'on the bases of suppliers certification data.

The inservice inspection program for the Reactor Coolant Pump flywheels is in conformance with the guidelines in Regulatory Guide 1.14.

f R& cC H) **4-h st{c cM in Sed, 5.2.7 REACTOR COOLANT PRESSURE BOUNDARY LEAKAGE DETECTION SYSTEMS 5.2.7.1 Leakage Detection Methods Two types of Reactor Coolant System leakage are considered for purposes of leakage detection - (1) leakage to other systems and (2) leakage to the Containment. Functional redundancy is provided by the use of diverse monitoring methods. The sensitivities indicated below are typical for the various types of instmments planned.

l Reactor coolant leakage to the Main Steam and Feedwater Systems via steam generator tube leaks is detected by two activity monitors located on the steam generator blowdown and condenser air ejector effluents (refer to Sections 11.4.2.1.4, " Steam Generator Blowdown Recycle Demineralizer Effluent Monitor" and 11.4.2.2.2, " Condenser Air Ejector Monitor" for discussion of monitors). Table 5-30 presents information about these detectors and their leak detection sensitivities. Positive indication of secondary system activity is provided in the Control Room. Leakage into the Component Cooling System via the Residual lleat Removal System is detected by activity monitors on the component cooling heat exchangers (see Section 9.2.4.3, " Safety Evaluation").

d 5-50 (15 FEB 1999)

n INSERT FOR UFSAR i

.An inservice inspection program is maintained for-the reactor coolant pump flywheels. This program provides for the inspection of5each reactor coolant pump. flywheel, as stated below, per the actions of.-Regulatory Guide 1.14 or the recommendations of Westinghouse Electric Corporation Topical Report WCAP-14535A,

" Topical Report _on ReactoriCoolantLPump Flywheel Inspection Elimination," dated November 1996.

The accept' ability for referencing this. topical report in lieu of Positions C.4.b(1) and C.4.b (2) ' of Regulatory Guide 1.14 was approved by NRC. letter and safety evaluation dated September 12, 1996.

Ten year : Inspection Requirement:

In lieu of Position C.4.b(1) and C.4.b(2) of Regulatory Guide 1.14, a qualified in-place UT examination over the volume from the inner bore of.the flywheel to the circle one-half of the

' outer radius or a surface examination (MT and/or PT) of exposed surfaces.of the. removed flywheels may be conducted at approximately 10 year intervals coinciding with the Inservice

' Inspection schedule as required by ASME Section XI.

1 I

McGuire Nuclear Station Appendix 5. Chapter 5 Tables and Figures Table 5-36. Reactor Coolant Pump Quality Assurance Program RT*

UT*

PT*

MT*

Castings yes yes Fornings

1. Main Shaft yes yes
2. Main Studs yes yes
3. Flywheel (Rolled Plate) yes yes
e. 5 (For 5

Bore)

Weldments

~

- 1. Circurnferential yes yes

2. Instrument Connections yes Note:

RT - Radiographic RT - Radiographic UT - Ultrasonic PT - Dye Penetration MT - Magnetic Particle Table 5-37. Steam Generator Design Data Design pressure, reactor coolant side, psig 2485

' Design pressitre, steam side, psig 1185 Design temperature, reactor coolant side, 'F 650 Design temperature, steam side *F 600 6

Total heat transfer surface area ft2 79,800 Maximum moisture, canyover, wt percent 0.25 6

Overall height, ft-in.

68'- 1 3/8" 6

Number of U-tubes 6633 6

Tube wall thickness, nominal, in.

0.040 6

U-tube outer diameter, in.

0.6875 6

Number of manways 3

6 Number of handholes 10 ID of handholes, in.

6 6

ID of manways, in.

21 6

6 1

(01 JAN 1998)

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<e b Catawba Units 1 and 2 Updated Final Safety Analysis Report Page 5-56 and Table 5-24 Marked Version l

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5.4 Comeponent and Subsystem Design Cattwba Nuclear Station The anti-reverse rotation device prevents reverse rotation with a maxunum reverse movement ofless than

]

j 5*.

5.4.1.3.10 Shaft Seal Leakage Ixakage along the reactor coolant pump shaft is controlled by three shaft seals arranged in series.

Chargmg flow is duected to each reactor coolant pump via a seal water injection filter. It enters the pump through a connection on the thermal banier flange and is duccted down to a point between the pump radial bearing and the thermal barrier heat enhanaer. IIere the flow splits. A portion flows down past the thermal barrier heat exchanger and into the Reactor Coolant System; the remamder flows up the pump shaft annuSs and enters the number 1 seal. Above the seal most of the flow leaves the pump via the number 1 seal discharge line. Minor flow passes through the number 2 seal and discharge line and the number 3 seal and the discharge line. This arrangement assures essentially zero leakage of reactor coolant er trapped gases from the pump.

5.4.1.3.11 Seal Discharge Piping Discharge pressure from the number I seal is reduced to that of the volume control tank. Water from each number 1 sealis piped to a common manifold, and through the seal water return filter and through the seal water heat excht.nger where the temperature is reduced to that of the volume control tank. The number 2 and number 3 leakofflines route number 2 and 3 sealleakage to the reactor coolant drain tank.

5.4.1.4 Tests and inspections The reactor coolant pumps can be inspected in accordance with ASME Section XI, Code for Inservice Inspection of Nuclear Reactor Coolant Systems.

The pump casing is cast in one piece, elimmating welds in the casing. Support feet are cast integral with the casing to eliminate a weld region.

The design enables disassembly and removal of the pump internals for usual access to the internal surface of the pump casing.

l The reactor coolant pump quality assurance program is given in Table 5-24.

5.4.1.5 Pump Flywheels The integrity of the reactor coolant pump flywheel is assured on the basis of the follcwing design and 7

quality assurance procedures. Regulatory Guide 1.14 is further discussed in Section 1.7, " Regulatory 7

Guides."

d 4-5.4.1.5.1 ign Basis

!CLC f CA 0 e, The calculated stresses at operating speed are based on stresses due to centrifugal forces. The stress resuhmg from the interference fit of the flywheel on the shaft is less than 2000 psi at zero speed, but this streu becomes zero at approximately 600 rpm because of radial expansion of the hub. The pnmary 7

coolant pumps run at approximately 1190 rpm and may operate briefly at overspeeds up to 111.5 percent 7

(1326 rpm) during loss of outside load. For conservatism, however,125 percent of operating speed was selected as the design speed for the pnmary coolant pumps. 'lle flywheels are given a preoperational test cf 125 percent of the maxunum synchronous speed of the motor.

_ ]

5-56 (24 OCT 1998) j

)

INSERT FOR UFSAR An inservice inspection program is maintained for the reactor coolant pump flywheels. This program provides for the inspection of each reactor coolant pump flywheel, as stated below, per the actions of Regulatory Guide 1.14 or the recommendations of Westinghouse Electric Corporation Topical Report WCAP-14535A,

" Topical Report on Reactor Coolant Pump Flywheel Inspo:ction Elimination," dated November 1996.

The acceptabilit. for referencing this topical report in lieu Position 4 C. 4.b (1) and C.4.b (2) of Regulatory Guide 1.14 wa approved

>y NRC letter an? safety evaluation dated September 12, 1996.

Ten year Inspection Requirement:

In lieu of Position C.4.b(1) and C.4.b (2) of Regulatory Guide 1.14, a qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle one-half of the outer radius or a surface examination (MT and/or PT) 'of exposed j

surfaces of the removed flywheels may be conducted at 1

approximately 10 year intervals coinciding with the Inservice

{

Inspection schedule as required by ASME Section XI.

i

)

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Catawba Nuclear Stat!.m Appendix 5. Chapter 5 Tables and Figures I

\\

l Table 5-24. steactor Coolant Pump Quality Assurance Program RT*

UT*

PT*

MT*

Castinas yes yes l

I Forainas l

l

1. Main Shaft yes yes
2. Main Studs yes yes
3. FlywheeltRolled Plate)

'jes yes yes Weldments '

j

(

l. Circumferential yes yes
2. Instrument Connections yes Notes:
  • RT - Radiographic
  • UT Ultrasonic
  • PT Dye Penetrant
  • MT Magnetic Particle I

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(el OCT 1991)

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