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Proposed Alternative to American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-729-1 Examination Requirements (Request No. 2-TYP-3-RV-02)
	ML090020385
Person / Time
Site:	Beaver Valley
Issue date:	12/30/2008
From:	Sena P P; FirstEnergy Nuclear Operating Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	2-TYP-3-RV-02, L-08-363
	Download: ML090020385 (35)
	v • d • e

FENOC Beaver Valley Power Station 0 %%P.O. Box 4'FirstEnergy Nuclear Operating Company Shippingport, PA 15077 Peter P. Sena III 724-682-5234 Site Vice President Fax: 724-643-8069 Withhold From Public Disclosure Under 10 CFR 2.390 When separated from Enclosure B, This Document Can Be Decontrolled December 30, 2008 L-08-363 10 CFR 50.55a(a)(3)(i)

ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001

SUBJECT:

Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 Proposed Alternative to American Society of Mechanical Enqineers Boiler and Pressure Vessel Code Case N-729-1 Examination Requirements (Request No. 2-TYP-3-RV-02)

Pursuant to 10 CFR 50.55a(a)(3)(i), FirstEnergy Nuclear Operating Company (FENOC)hereby requests Nuclear Regulatory Commission (NRC) approval of a proposed alternative to American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) Case N-729-1 volumetric and surface examination coverage requirements for certain Beaver Valley Power Station Unit No. 2 (BVPS-2) reactor vessel head penetrations.

This request for NRC approval is required by 10 CFR 50.55a(g)(6)(ii)(D)(6).

The proposed alternative provides an acceptable level of quality and safety and is described in detail in Enclosure A.FENOC requests approval of the proposed alternative by October 5, 2009 to permit implementation of the alternative during the fourteenth BVPS-2 maintenance and refueling outage. The maintenance and refueling outage is scheduled to begin in October 2008.Westinghouse Technical Report WCAP-16144, "Structural Integrity Evaluation of Reactor Vessel Upper Head Penetrations to Support Continued Operation:

Beaver Valley Unit 2," was used as a basis for this request. WCAP-16144 is considered proprietary information and should be withheld from public disclosure under 10 CFR 2.390.Four copies of WCAP-16144-P, Revision 1, "Structural Integrity Evaluation of Reactor Vessel Upper Head Penetrations to Support Continued Operation:

Beaver Valley Unit 2," (Proprietary) are provided as Enclosure B.4-, 4-hp PM to Beaver Valley Power Station, Unit No. 2 L-08-363 Page 2 Withhold From Public Disclosure Under 10 CFR 2.390 When separated from Enclosure B, This Document Can Be Decontrolled Four copies of WCAP-16144-NP, Revision 1, "Structural Integrity Evaluation of Reactor Vessel Upper Head Penetrations -to Support Continued Operation:

Beaver Valley Unit 2," (Non-Proprietary) are provided as Enclosure C.As Enclosure B contains information proprietary to Westinghouse Electric Company LLC, it is supported by an affidavit signed by Westinghouse, the owner of the information.

The affidavit provided in Enclosure D sets forth the basis on which the information may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in paragraph (b)(4) of Section 2.390 of the Commission's regulations.

Westinghouse's Proprietary Information Notice and Copyright Notice are also provided in Enclosure D.Accordingly, it is respectfully requested that the information which is proprietary to Westinghouse be withheld from public disclosure in accordance with 10 CFR Section 2.390 of the Commission's regulations.

Correspondence with respect to the copyright or proprietary aspects of Enclosures B and C, or the supporting Westinghouse Affidavit, should reference CAW-08-2505 and should be addressed to J. A. Gresham, Manager', Regulatory Compliance and Plant Licensing, Westinghouse Electric Company LLC, P.O. Box 355, Pittsburgh, Pennsylvania 15230-0355.

There are no regulatory commitments contained in this submittal.

If there are any questions or if additional information is required, please contact Mr. Thomas A. Lentz, Manager -Fleet Licensing, at 330-761-6071.

Sincerely, Peter P. Sena III

Enclosures:

A. 10 CFR 50.55a Request Number 2-TYP-3-RV-02 B. Structural Integrity Evaluation of Reactor Vessel Upper Head Penetrations to Support Continued Operation:

Beaver Valley Unit 2 (Proprietary)

C. Structural Integrity Evaluation of Reactor Vessel Upper Head Penetrations to Support Continued Operation:

Beaver Valley Unit 2 (Non-Proprietary)

Beaver Valley Power Station, Unit No. 2 L-08-363 Page-3 Withhold From Public Disclosure Under 10 CFR 2.390 When separated from Enclosure B, This Document Can Be Decontrolled D. Westinghouse Authorization Letter (CAW-08-2505), Accompanying Westinghouse Affidavit, Proprietary Information Notice, and Copyright Notice.cc: NRC Region I Administrator (w/o enclosures)

NRC Senior Resident Inspector (w/o enclosures)

NRR Project Manager (w/o enclosures)

Director BRP/DEP (w/o enclosures)

Nuclear Safety Specialist BRP/DEP (w/o enclosures)

Enclosure A Letter L-08-363 10 CFR 50.55a Request Number 2-TYP-3-RV-02 Page 1 of 26 Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(i) 2 1.0 ASME Code Components Affected Component Numbers: Beaver Valley Power Station Unit No. 2 (BVPS-2) Reactor Vessel (2RCS-REV-21)

Head Penetrations 1, 3, 5 through 34, 37, 38, 41, 42, 43, 45, 46, 48, 49, and 54 through 65 Code Class: 1 Examination Category:

PWR Reactor Vessel Upper Head Item Number: B4.20

Description:

UNS N06600 nozzles and UNS N06082 or UNS W86182 partial-penetration welds in head 2.0 Applicable Code Edition And Addenda American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code)Section XI, 2001 Edition through 2003 Addenda.3.0 Applicable Code Requirements The Code of Federal Regulations 10CFR50.55a(g)(6)(ii)(D)(1) requires that examinations of the reactor vessel head be performed in accordance with ASME Code Case N-729-1 (Reference 8.1), subject to the conditions specified in paragraphs 10CFR50.55a(g)(6)(ii)(D)(2) through (6).Paragraph 2500 of Code Case N-729-1 states, in part: "... If obstructions or limitations prevent examination of the volume or surface required by Fig. 2 for one or more nozzles, the analysis procedure of Appendix I shall be used to demonstrate the adequacy of the examination volume or surface for each such nozzle. If Appendix I is used, the evaluation shall be submitted to the regulatory authority having jurisdiction at the plant site." Figure 2, as referenced by paragraph 2500, requires that the volumetric or surface examination coverage distance below the toe of the J-groove weld (dimension "a") be 1.5 inches for incidence angle "6" less than or equal to 30 degrees, or 1 inch for incidence angle "0" greater than 30 degrees; or to the bottom of the tube, whichever is less. These coverage requirements are applicable to the BVPS-2 reactor vessel head penetrations as follows:

Enclosure A L-08-363 Page 2 of 26 Incidence Angle, "0" Required Coverage, "a" Penetrations (degrees) (inches)1 to 33 < 30 1.5 34 to 65 > 30 1.0 4.0 Reason For Request The bottom end of all of the BVPS-2 reactor vessel head control rod drive mechanism (CRDM) penetrations are externally (outside diameter or "OD") threaded, internally (inside diameter or "ID") tapered, and have an ultrasonic corner shadow zone produced by the thread relief, precluding ultrasonic or eddy current data acquisition in a zone extending up approximately 1.45 inches from the bottom of each nozzle. For the majority of the penetrations, these geometric limitations reduce the inspectable distance from the bottom of the J-groove weld fillet to the top of the thread relief to some value less than the required coverage dimension "a" shown in Figure 2 of Code Case N-729-1.During the BVPS-2 fall 2003 refueling outage (2R1 0), FENOC obtained examination coverage data on all 65 CRDM penetrations in the reactor vessel head. This information was used to support FENOC's previous NRC Order Relaxation Request regarding examination coverage below the J-groove Figure 1: Reactor Vessel-weld, which was approved by the NRC (References 8.2, Head Penetration 8.3, 8.4 and 8.5). However, the issuance of 10 CFR 50.55a(g)(6)(ii)(D), Reactor vessel head inspections, on 6 t25" -September 10, 2008 requires implementation of Code Case N-729-1 with NRC conditions by December 31, J-wed 6lo 2008. Once a licensee implements the provisions of 10 'Downhill' Tube CFR 50.55a(g)(6)(ii)(D), the Order and all previously Side approved relaxations no longer apply. OD ID Figure 1 and Table 1 show the geometry of the BVPS-2 reactor vessel head penetrations and the attainable A examination coverage (in inches) below the toe of the J- I groove weld fillet on the 'downhill' (limiting) side of each 0 penetration.

Based upon the measured values listed in Table 1, T deviation from the coverage requirements of ASME Code Case N-729-1 with respect to the volumetric and l 75" surface examinations of Item B4.20 is necessary.

Specifically, deviation from the required 1.5 inches for F0314- /reactor vessel head penetrations 1, 3, and 5 through 33 (with incidence angles less than or equal to 30 degrees) 20o and from the required 1 inch for reactor vessel head Unexamined Region penetrations 34, 37, 38, 41, 42, 43, 45, 46, 48, 49, and I 54 through 65 (with incidence angles greater than 30 degrees) is necessary.

Enclosure A L-08-363 Page 3 of 26 Table 1: Inspection Coverage Obtained on the CRDM Penetration "Downhill" Side Penetration Measured Inspection Number Dimension Coverage"A" Obtained"B" 1 1.64 1.44 2 1.88 1.68 3 1.52 1 1.32 4 1.72 1.52 5 1.44 1.24 6 1.46 1.26 7 1.40 1.20 8 1.32 1.12 9 1.60 1.40 10 1.60 1.40 11 1.28 1.08 12 1.60 1.40 13 1.56 1.36 14 1.52 1.32 15 1.40 1.20 16 1.64 1.44 17 1.46 1.26 18 1.32 1.12 19 1.36 1.16 20 1.20 1.00 21 1.52 1.32 22 1.28 1.08 23 1.40 1.20 24 1.48 1.28 25 1.40 1.20 26 1.24 1.04 27 1.44 1.24 28 1.32 1.12 29 1.08 0.88 30 1.20 1.00 31 1.60 1.40 32 1.44 1.24 33 1.32 1.12 Penetration Measured Inspection Number Dimension Coverage"A" Obtained"B" 34 1-.12 0.92 35 1.60 1.40 36 1.28 1.08 37 1.08 0.88 38 1.04 0.84 39 1.36 1.16 40 1.44 1.24 41 1.12 0.92 42 1.12 0.92 43 1.16 0.96 44 1.36 1.16 45 1.08 0.88 46 1.00 0.80 47 1.28 1.08 48 1.08 0.88 49 1.08 0.88 50 1.36 1.16 51 1.40 1.20 52 1.32 1.12 53 1.28 1.08 54 1.16 0.96'55 1.00 0.80 56 0.92 0.72 57 1.12 0.92 58 0.60 0.40 59 0.96 0.76 60 0.88 0.68 61 0.88 0.68 62 0.68 0.48 63 0.88 0.68 64 1.08 0.88 65 0.80 0.60 1 5.0 Proposed Alternative And Basis For Use As an alternative to the volumetric and surface examination coverage requirements shown as dimension "a" in Figure 2 of ASME Code Case N-729-1, FENOC proposes the use of attainable ultrasonic examination distances shown as Dimension "B" in Table 1 of this request. Specifically, in lieu of the required 1.5 inches for incidence angles less than or equal to 30 degrees (Penetrations 1, 3, and 5 through 33),' and th e required 1.0 inch for incidence angles greater than 30 degrees (Penetrations 34, 37, 38, 41, 42, 43, 45, 46, 48, 49, and 54 through 65), the examination coverage recorded as Dimension "B" in Table 1 above will be obtained.

For all other penetrations, the Enclosure A L-08-363 Page 4 of 26 required examination coverage dimension "a" reflected in Figure 2 of Code Case N-729-1 will be met or exceeded.

Table 2 provides the scope of this request as a sumnmary of the applicable N-729-1 examination coverage distances "a" (based upon incidence angle) and achievable examination coverage for each penetration.

Table 2: Scon~e of Request Pen. 0 "all Alternative Relief No.* (degrees) (inches) Coverage Requested 1 0.0 1.5 1.44 Yes 2 8.7 1.5 N/A No 3 8.7 1.5 1.32 Yes 4 18.7 1.5 1N/A No 5 8.7 1.5 1.24 Yes 6 12.4 1.5 1.26 Yes 7 12.4 1.5 1.20 Yes 8 12.4 1.5 1.12 Yes 9 12.4 1.5 1.40 Yes 10 17.6 1.5 1.40 Yes 11 17.6 1.5 1.08 Yes 12 17.6 1.5 1.40 Yes 13 17.6 1.5 1.36 Yes 14 19.8 1.5 1.32 Yes 15 19.8 1.5 1.20 Yes 16 19.8 1.5 1.44 Yes 17 19.8 1.5 1.26 Yes 18 25.4 1.5 1.12 Yes 19 25.4 1.5 1.16 Yes 20 25.4 1.5 1.00 Yes 21 25.4 1.5 1.32 Yes 22 27.0 1.5 1.08 Yes 23 27.0 1.5 1.20 Yes 24 27.0 1.5 1.28 Yes 25 27.0 1.5 1.20 Yes 26 28.6 1.5 1.04 Yes 27 28.6 1.5 1.24 Yes 28 28.6 1.5 1.12 Yes 29 28.6 1.5 0.88 Yes 30 28.6 1.5 1.00. Yes 31 28.6 1.5 1.40 Yes 32 28.6 1.5 1.24 Yes 33 28.6 1.5 1.12 Yes*Penetration Number Pen. 6 "all Alternative Relief No.* (degrees) (inches) Coverage R 'equested 34 33.1 1.0 0.92 Yes 35 33.1 1.0 N/A No 36 33.1 1.0 N/A No 37 133.1 1.0 0.88 Yes 38 33.1 1.0 0.84 Yes 39 33.1 1.0 N/A No 40 33.1 1.0 N/A No 41 33.1 1.0 0.92 Yes 42 37.3 1.0 0.92 Yes 43 37.3 1.0 0.96 Yes 44 37.3 1.0 N/A No 45 37.3 1.0 0.88 Yes 46 38.7 1.0 0.80 Yes 47 38.7 1.0 N/A No 48 38.7 1.0 0.88 Yes 49 38.7 1.0 0.88 Yes 50 38.7 1.0 N/A No 51 38.7 1.0 N/A No 52 38.7 1.0 N/A No 53 38.7 1.0 N/A No 54 40.0 1.0 0.96 Yes 55 40.0 1.0 0.80 Yes 56 40.0 1.0 0.72 Yes 57 40.0 1.0 0.92 Yes 58 42.7 1.0 0.40 Yes 59 42.7 1.0 0.76 Yes 60 42.7 1.0 0.68 Yes 61 42.7 1.0 0.68 Yes 62 42.7 1.0 0.48 Yes 63 42.7 1.0 0.68 Yes 64 42.7 1.0 0.88 Yes 65 42.7 1.0 0.60 Yes Enclosure A L-08-363 Page 5 of 26 Appendix I of ASME Code Case N-729-1 provides the analysis procedure for the evaluation of an alternative examination area or volume to that specified in Figure 2 of the Code Case if impediments prevent the examination of the complete zone. As discussed previously, the BVPS-2 reactor vessel head CRDM penetrations are externally (OD) threaded and internally (ID) tapered, precluding ultrasonic or eddy current data acquisition of the complete zone defined by the Code Case for Penetrations 1, 3, 5 through 33, 34, 37, 38, 41, 42, 43, 45, 46, 48, 49, and 54 through 65.Section 1-1000;of ASME Code Case N-729-1 requires that for alternative examination zones that eliminate portions of the Figure 2 examination zone below the J-groove weld, the analyses shall be performed using at least the stress analysis method (1-2000) or the deterministic fracture mechanics analysis method (1-3000) to demonstrate that the applicable criteria are satisfied.

In support of this request, the techniques of both 1-2000 and Method 1 of 1-3200 were performed and are included in Reference 8.6, provided with this request.5.1 Stress Analysis in Accordance with 1-2000 Section 1-2000 of ASME Code Case N-729-1 requires that plant-specific analysis demonstrate that the hoop and axial stresses remain below 20,000 pounds per square inch (tensile) over the entire region outside the alternative examination zone but within the examination zone defined in Figure 2. Analyses were performed for five different CRDM geometries, including the outermost row (at 42.7 degrees angular position from the reactor vessel centerline), rows at 40.0 degrees, 38.7 degrees, 25.4 degrees and the center location.

The actual achievable ultrasonic examination coverage dimensions obtained during the fall 2003 inspection were used to define the alternative examination zone. A summary of bounding penetration geometries and examination coverage distances are shown in Table 3.i Table 3: BVPS-2 Bounding Analyses and Minimum Inspection Coverage Below the J-Groove Weld Penetration Minimum Achievable Nozzle Nos. Analyzed Inspection Coverage Reference

8.6 Bounded

By the Penetration Distance below the bottom Figure No. Analyzed Nozzle Nozzle of the weld (inches)A-1 1-17 00 1.08*A-2 (Downhill) 18 -45 25.40 0.84 A-3 (Uphill) 3.16 A-4 (Downhill) 46 -53 38.70 0.80 A-5 (Uphill) 4.32 A-6 (Downhill) 54 -57 40.00 0.72 A-7 (Uphill) 4.76 A-8 (Downhill) 58-65 42.70 0.40 A-9 (Uphill) 4.88*Applicable to both downhill and uphill side of Penetration Nozzle No. 2 to 17 (

Enclosure A L-08-363 Page 6 of 26 The stress analysis methodology and conclusions are in Section 5 of Reference 8.6.The hoop stress distribution plots for the analyzed geometries are provided in figures A-1 through A-9 of this enclosure (Note that in all cases the hoop stresses during steady state operation dominate the axial stresses.

See Sections 5.3 through 5.5 of Reference 8.6). The minimum inspection zones shown in figures A-1 through A-9 represent the minimum achievable inspection coverage distances for each bounding configuration as shown in Table 3 above.The hoop stress distribution plots in figures A-1 through A-9 demonstrate that in all cases, the stresses remain below 20,000 pounds per square inch (tensile) over the entire region outside the alternative examination zone but within the examination zone defined in Figure 2 as required by 1-2000 of N-729-1.5.2 Deterministic Fracture Mechanics Analysis in Accordance with 1-3200, Method 1 In addition to the stress analysis detailed above, a fracture mechanics analysis was performed in accordance with Method 1 of 1-3200 to demonstrate that a potential axial crack in the unexamined zone will not grow to the toe of the J-groove weld prior to the next scheduled examination.

Because previous penetration repairs have been required on the BVPS-2 reactor vessel head, the re-examination frequency is every refueling outage (every 18 months) per 1OCFR50.55a(g)(6)(ii)(D)(5).

The complete fracture mechanics analysis is provided in Section 6 of Reference 8.6, and was performed using input from the previously discussed stress analysis and bounding penetration geometries.

The results of the analysis are shown as flaw tolerance charts which can be used to determine the minimum required inspection coverage to ensure that any flaws initiated below the weld in the region of the penetration nozzle not being inspected would not reach the bottom of the weld before the next inspection (Figures 6-12 through 6-20 of Reference 8.6). These crack growth projections are also provided in figures B-1 through B-9 of this enclosure.

In accordance with Method 1 of 1-3200, the crack growth calculations performed to produce the flaw tolerance charts assume the initial upper extremity of the through-wall flaw to be at or within the bottom edge of the alternative examination zone, and the lower extremity to be located on the penetration nozzle where either the inside or the outside surface hoop stress becomes compressive.

The average of inside and outside surface hoop stress was applied along the entire length of the assumed through-wall crack and the stress intensity factor was calculated using the standard expression for an axial through-wall crack in a cylinder.

The crack growth rate determination was made in accordance with Appendix 0 of the 2004 Edition ASME Xl.The resulting flaw tolerance charts in figures B-1 through B-9 demonstrate that a postulated through-wall flaw at the bottom edge of the proposed alternative examination zone will not grow to the toe of the J-groove weld within the 18-month inspection Enclosure A L-08-363 Page 7 of 26 interval.

In all cases, the crack growth predictions show greater than four years of full power operation required to grow the postulated flaw to the toe of weld. Additionally, the initial upper extremity locations of axial through-wall flaws assumed in figures B-1 through B-9 are conservative based on a review of the achievable inspection coverage zone in Table 2 of this request because all the assumed upper crack extremities are located within the achievable inspection zone.The above proposed alternative examination zones for BVPS-2 CRDM penetrations 1, 3, 5 through 33, 34, 37, 38, 41, 42, 43, 45, 46, 48, 49, and 54 through 65 are supported by Appendix I of Code Case N-729-1 utilizing both the stress analysis criteria of 1-2000 and the deterministic fracture mechanics criteria of 1-3200, and thus provide an acceptable level of quality and safety.6.0 Duration Of Proposed Alternative The duration of the proposed alternative is for the remainder of the BVPS-2 third ten-year inservice inspection interval scheduled to end in 2018.7.0 Precedent Due to the recent issuance of NRC Rule changes in 10CFR50.55a(g)(6)(ii)(D) and ASME Code Case N-729-1, no specific precedent was found regarding deviation from the examination coverage requirements of the ASME Code Case or the use of Appendix I. Relaxations to the requirements of NRC Order EA-03-009 were submitted and approved by the NRC for BVPS-2 (References 8.2, 8.3, 8.4 and 8.5). The previously approved relaxation request for BVPS-2 applied to all of the 65 CRDM penetrations in the reactor vessel head under the requirements of the initial issuance of the Order, and was based on Revision 0 of Reference 8.6. The current request applies to a total of 53 of the 65 CRDM penetrations due to the same geometric limitations encountered in satisfying the Order requirements.

Revision 1 of Reference 8.6 was prepared in support of this request to ensure compliance with the requirements of Appendix I of ASME Code Case N-729-1.8.0 References 8.1 ASME Code Case N-729-1, "Alternative Examination Requirements for PWR[pressurized water reactor (PWR)] Reactor Vessel Upper Heads With Nozzles Having Pressure-Retaining Partial-Penetration WeldsSection XI, Division 1." 8.2 FENOC Letter L-03-088, "Order (EA-03-009)

Relaxation Request," dated July 29, 2003.8.3 FENOC Letter L-03-198, "Supplement to Order (EA-03-009)

Relaxation Request," dated December 19, 2003.8.4 FENOC Letter L-04-006, "Transmittal of WCAP-16144-P for Order (EA-03-009)

Relaxation Request," dated January 27, 2004.

Enclosure A L-08-363 Page 8 of 26 8.5 NRC letter "Relaxation of the Requirements of Order EA-03-009, Dated February 11, 2003, Regarding Examination Coverage for Reactor Pressure Vessel Head Penetration Nozzles for Beaver Valley Power Stations, Unit No. 2 (TAC. No.MC0237)," dated August 2, 2004.8.6 Westinghouse Technical Report WCAP-16144-P, Revision 1, "Structural Integrity Evaluation of Reactor Vessel Upper Head Penetrations to Support Continued Operation:

Beaver Valley Unit 2," dated December 2008.

Enclosure A L-08-363 Page 9 of 26 Figure A-1 Hoop Stress Distribution Below the Weld Downhill and Uphill Side (00 CRDM Penetration Nozzle)70,000 , MinimurnI Inspection Zone I I 50.000 -- ----- -- ----- -----30.0110----------------J---

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Enclosure A L-08-363 Page 19 of 26 Figure B-2 Through-Wall Axial Flaws Located in the 25.4 Degrees Row of Penetrations, Uphill Side 2.5 2.0 C Z;0 1.5 E m S C3 S1.0 o -0.5 I I i I i I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I F I TI I I I I I I I I I I I I I I I I --I '-7.1 I .J _ JL ..I _L L_ -I J -I L _ _L _ J _ _ .-L _ .L J J _L -I --J L. -L _J _ -L -L. _ .J. .. ... _ i I I I I I I I I I I I I I I I I I I I I I I I i I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I----, ----,--r-- ----------- -----r---r-- r,, ---I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I2 I I I I I I I I_ ._ _ L _ J -. ... L _--_ _-L ... .-_ _ I -.. .L- -L. J ._ _. .. --L ..--L -=J ...= -.J -I I II I I I I I I/ / / I I I I I I I I I I I I I I I I I I---- -------- ---------

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Enclosure A L-08-363 Page 20 of 26 Figure B-3 Through-Wall Axial Flaws Located in the 25.4 Degrees Row of Penetrations, Downhill Side 2.5 E~0 C S u'-0 I-,U 2.0 1.5 1.0 0.5 0.0-0.5+/- JL!L .JIL.1 LL-J-JJ-.

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Enclosure A L-08-363 Page 21 of 26 Figure B-4 Through-Wall Axial Flaws Located in the 38.7 Degrees Row of Penetrations, Uphill Side 2-5 CL 20 0 2-0 I .5 1.0.0.5 0.0-0.5 I I I I I I I I I I I I ! ! ! I I I ! I I I I III I I I I i i i --I- m I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I i I I I I I I I I I I I I I I I I I S I I I s I l I I I I / I I I I I I I I I I I I I I I I I I I I---- ---------------.

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Enclosure A L-08-363 Page 22 of 26 Figure B-5 Through-Wall Axial Flaws Located in the 38.7 Degrees Row of Penetrations, Downhill Side 2.5 2.0 Z: 05 1.5 K a m S o 1.0 D.-I-4 0.5 n .-0.5 I I I I i i I I I I I I I I I I I I I I III i i I i i I I I I i I I I I I I I I I I I I I I III I I I I I I I I I I I I ---- --- --- --- ---- ------- ---T--- -- -T ---r--=----rr r -l l I I I I i ii I I I I I I I I i i I I I I I I----I I -I I -I I I I I I I I I I I I_ I4 I I I 7' I I I I J .J L. .I L.. .-. LJ.J L _ .J. _. _ L J I I I L _ ,L L .... ...I I I I I II I I I I -I I I I I I I I I I L _I I I I I I I I I II I II I I II I I II I I I I I I I I I I--------------

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Enclosure A L-08-363 Page 23 of 26 Figure B-6 Through-Wall Axial Flaws Located in the 40.0 Degrees Row of Penetrations, Uphill Side 2-5 0 E.0 0 0i 0 CL C3 2-0 1.5 1.0 0.5 0.0-0-5 I I I I I I I I I I I l I I I I I I I I I I I I I I I I I I I l I I I I I I I I I I I l I I I I I I I I I I I I I I I I I I I I I ----LI L _ I J _ L I I I -

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'1 Enclosure A L-08-363 Page 24 of 26 Figure B-7 Through-Wall Axial Flaws Located in the 40.0 Degrees Row of Penetrations, Downhill Side 2-5 I I I I---4.-- -I----I---.

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CAW-08-2505 AFFIDAVIT COMMONWEALTH OF PENNSYLVANIA:

ss COUNTY OF ALLEGHENY:

Before me, the undersigned authority, personally appeared J. A. Gresham, who, being by me duly sworn according to law, deposes and says that he is authorized to execute this Affidavit on behalf of Westinghouse Electric Company LLC (Westinghouse), and that the averments of fact set forth in this Affidavit are true and correct to the best of his knowledge, information, and belief:/J. A. Gresham, Manager Regulatory Compliance and Plant Licensing Sworn to and subscribed before me this 9th day of December, 2008 Notary Public COMMONWEALTH OF PENNSYLVANIA Notarial Seal Sharon L Markle, Notary Public Monroevilie Boro, Allegheny County My Commission Expires Jan. 29,2011 Member, Pennsylvania Association of Notaries 2 CAW-08-2505 (1) 1 am Manager, Regulatory Compliance and Plant Licensing, in Nuclear Services, Westinghouse Electric Company LLC (Westinghouse), and as such, I have been specifically delegated the function of reviewing the proprietary information sought to be withheld from public disclosure in connection with nuclear power plant licensing and rule making proceedings, and am authorized to apply for its withholding on behalf of Westinghouse.

(2) I am making this Affidavit in conformance with the provisions of 10 CFR Section 2.390 of the Commission's regulations and in conjunction with the Westinghouse "Application for Withholding" accompanying this Affidavit.

(3) I have personal knowledge of the criteria and procedures utilized by Westinghouse in designating information as a trade secret, privileged or as confidential commercial or financial information.

(4) Pursuant to the provisions of paragraph (b)(4) of Section 2.390 of the Commission's regulations, the following is furnished for consideration by the Commission in determining whether the information sought to be withheld from public disclosure should be withheld.(i) The information sought to be withheld from public disclosure is owned and has been held in confidence by Westinghouse.(ii) The information is of a type customarily held in confidence by Westinghouse and not customarily disclosed to the public. Westinghouse has a rational basis for determining the types of information customarily held in confidence by it and, in that connection, utilizes a system to determine when and whether to hold certain types of information in confidence.

The application of that system and the substance of that system constitutes Westinghouse policy and provides the rational basis required.Under that system, information is held in confidence if it falls in one or more of several types, the release of which might result in the loss of an existing or potential competitive advantage, as follows: (a) The information reveals the distinguishing aspects of a process (or component, structure, tool, method, etc.) where prevention of its use by any of Westinghouse's competitors without license from Westinghouse constitutes a competitive economic advantage over other companies.

3 CAW-08-2505 (b) It consists of supporting data, including test data, relative to a process (or component, structure, tool, method, etc.), the application of which data secures a competitive economic advantage, e.g., by optimization or improved marketability.(c) Its use by a competitor would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing a similar product.(d) It reveals cost or price information, production capacities, budget levels, or commercial strategies of Westinghouse, its customers or suppliers.(e) It reveals aspects of past, present, or future Westinghouse or customer funded development plans and programs of potential commercial value to Westinghouse.(f) It contains patentable ideas, for which patent protection may be desirable.

There are sound policy reasons behind the Westinghouse system which include the following: (a) The use of such information by Westinghouse gives Westinghouse a competitive advantage over its competitors.

It is, therefore, withheld from disclosure to protect the Westinghouse competitive position.(b) It is information that is marketable in many ways. The extent to which such information is available to competitors diminishes the Westinghouse ability to sell products and services involving the use of the information.(c) Use by our competitor would put Westinghouse at a competitive disadvantage by reducing his expenditure of resources at our expense.(d) Each component of proprietary information pertinent to a particular competitive advantage is potentially as valuable as the total competitive advantage.

If competitors acquire components of proprietary information, any one component may be the key to the entire puzzle, thereby depriving Westinghouse of a competitive advantage.

4 CAW-08-2505 (e) Unrestricted disclosure would jeopardize the position of prominence of Westinghouse in the world market, and thereby give a market advantage to the competition of those countries.(f) The Westinghouse capacity to invest corporate assets in research and development depends upon the success in obtaining and maintaining a competitive advantage.(iii) The information is being transmitted to the Commission in confidence and, under the provisions of 10 CFR Section 2.390, it is to be received in confidence by the Commission.(iv) The information sought to be protected is not available in public sources or available information has not been previously employed in the same original manner or method to the best of our knowledge and belief.(v) The proprietary information sought to be withheld in this submittal is that which is appropriately marked in WCAP- 16144-P, Revision 1, "Structural Integrity Evaluation of Reactor Vessel Upper Head Penetrations to Support Continued Operation:

Beaver Valley Unit 2" (Proprietary), dated December 2008, for submittal to the Commission, being transmitted by the FirstEnergy Nuclear Operating Company letter and Application for Withholding Proprietary Information from Public Disclosure, to the Document Control Desk. The proprietary information as submitted by Westinghouse for Beaver Valley Unit 2 is expected to be applicable for other licensee submittals in response to certain NRC requirements for justification of relaxation requests regarding the examination of reactor vessel control rod drive mechanism (CRDM) head penetrations and the required examination coverage distances.

This information is part of that which will enable Westinghouse to: (a) Provide documentation on the analyses, methods and development of crack growth curves in support of similar relaxation requests for the inspection of reactor vessel CRDM head penetrations.(b) Assist the customer in obtaining NRC approval.

5 CAW-08-2505 Further this information has substantial commercial value as follows: N (a) The information reveals the distinguishing aspects of a process or component, structure, tool, method, etc., and the prevention of its use by Westinghouse's competitors, without license from Westinghouse, gives Westinghouse a competitive economic advantage.(b) The information, if used by a competitor, would reduce the competitor's expenditure of resources or improve the competitor's advantage in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product.(c) The information reveals aspects of past, present, or future Westinghouse or customer funded development plans and programs of potential commercial value to Westinghouse.

Public disclosure of this proprietary information is likely to cause substantial harm to the competitive position of Westinghouse because it would enhance the ability of competitors to provide similar calculations and licensing defense services for commercial power reactors without commensurate expenses.

Also, public disclosure of the information would enable others to use the information to meet NRC requirements for licensing documentation without purchasing the right to use the information.

The development of the technology described in part by the information is the result of applying the results of many years of experience in an intensive Westinghouse effort and the expenditure of a considerable sum of money.In order for competitors of Westinghouse to duplicate this information, similar technical programs would have to be performed and a significant manpower effort, having the requisite talent and experience, would have to be expended.Further the deponent sayeth not.

PROPRIETARY INFORMATION NOTICE Transmitted herewith are proprietary and/or non-proprietary versions of documents furnished to the NRC in connection with requests for generic and/or plant-specific review and approval.In order to conform to the requirements of 10 CFR 2.3 90 of the Commission's regulations concerning the protection of proprietary information so submitted to the NRC, the information which is proprietary in the proprietary versions is contained within brackets, and where the proprietary information has been deleted in the non-proprietary versions, only the brackets remain (the information that was contained within the brackets in the proprietary versions having been deleted).

The justification for claiming the information so designated as proprietary is indicated in both versions by means of lower case letters (a) through (f)located as a superscript immediately following the brackets enclosing each item of information being identified as proprietary or in the margin opposite such information.

These lower case letters refer to the types of information Westinghouse customarily holds in confidence identified in Sections (4)(ii)(a) through (4)(ii)(f) of the affidavit accompanying this transmittal pursuant to 10 CFR 2.390(b)(1).

COPYRIGHT NOTICE The reports transmitted herewith each bear a Westinghouse copyright notice. The NRC is permitted to make the number of copies of the information contained in these reports which are necessary for its internal use in connection with generic and plant-specific reviews and approvals as well as the issuance, denial, amendment, transfer, renewal, modification, suspension, revocation, or violation of a license, permit, order, or regulation subject to the requirements of 10 CFR 2.390 regarding restrictions on public disclosure to the extent such information has been identified as proprietary by Westinghouse, copyright protection notwithstanding.

With respect to the non-proprietary versions of these reports, the NRC is permitted to make the number of copies beyond those necessary for its internal use which are necessary in order to have one copy available for public viewing in the appropriate docket files in the public document room in Washington, DC and in local public document rooms as may be required by NRC regulations if the number of copies submitted is insufficient for this purpose. Copies made by the NRC must include the copyright notice in all instances and the proprietary notice if the original was identified as proprietary.

v t e Letter Sequence Request
TAC:ME0349, (Open)
Initiation Request, Request Acceptance... Administration Withholding Request Acceptance Questions Answers Results Approval... Other: ML092640111
MONTHYEAR2009-09-14 [Table View]

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ML090020385: Difference between revisions

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SUBJECT:

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Description:

8.6 Bounded

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