NOC-AE-16003425, Review and Comment of License Renewal Application Safety Evaluation Report with Open Items (TAC Nos. ME4936 and ME4937)

Review and Comment of License Renewal Application Safety Evaluation Report with Open Items (TAC Nos. ME4936 and ME4937)

ML17006A008
Person / Time
Site:	South Texas
Issue date:	12/14/2016
From:	Marc-Anthony Murray South Texas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NOC-AE-16003425, TAC ME4936, TAC ME4937
Download: ML17006A008 (10)

Text

Nuclear Operating Company South Texas Project Electric Generating Station P.O. Box 28.9 Wadsworth, Texas 77483 December 14, 2016 NOC-AE-16003425 10 CFR 54 File No. G25 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 South Texas Project Units 1 and 2 Docket Nos. STN 50-498, STN 50-499 STPNOC Review and Comment of License Renewal Application Safety Evaluation Report with Open Items (TAC NOS. ME4936 and ME4937)

References:

1. Letter; G. T. Powell to the NRC Document Control Desk; "License Renewal Application",

NOC-AE-10002607; dated October 25, 2010. (ML103010257)

2. Letter; NRC to STP Nuclear Operating Company; "Safety Evaluation Report With Open Items Related to STP Nuclear Operating Company, Units 1 and 2 (TAC No. ME4936 and ME4937)"; dated October 14, 2016. (ML16271A011)

By Reference 1, STP Nuclear Operating Company (STPNOC) submitted an application to the Nuclear Regulatory Commission (NRC) for the renewal of Facility Operating Licenses NPF-76 and NPF-80, for South Texas Project (STP) Units 1 and 2, respectively. In Reference 2, the NRC transmitted the Safety Evaluation Report (SER) with Open Items related to the license renewal of the South Texas Project, Units 1 and 2. STPNOC is providing review comments to the License Renewal Safety Evaluation Report, Reference 2.

There are no regulatory commitments in this letter.

STI: 34416560

NOC-AE-16003425 Page 2 of 3 Should you have any questions regarding this letter, please contact Arden Aldridge, STP License Renewal Project Lead, at (361) 972-8243, or Rafael Gonzales, STP License Renewal Project regulatory point-of-contact, at (361) 972-4779.

Michael P. Murray Manager, Regulatory Affairs rjg

Enclosure:

Comments Regarding the Safety Evaluation Report (SER) with Open Items Dated October 2016 Related to the License Renewal of South Texas Project, Units 1 and 2

NOC-AE-16003425 Page 3 of 3 cc:

(paper copy) (electronic copy)

Regional Administrator, Region IV Morgan, Lewis & Bockius LLP U.S. Nuclear Regulatory Commission Steve Frantz 1600 East Lamar Boulevard Arlington, TX 76011-4511 U.S. Nuclear Regulatory Commission Lisa M. Regner Lisa M. Regner Lois James Senior Project Manager Tam Tran U.S. Nuclear Regulatory Commission One White Flint North (MS 8 G9A) 11555 Rockville Pike NRG South Texas LP Rockville, MD 20852 Chris O'Hara Jim van Suskil Skip Zahn NRC Resident Inspector U. S. Nuclear Regulatory Commission P. 0. Box 289, Mail Code: MN116 CPS Energy Wadsworth, TX 77 483 Kevin Pollo Cris Eugster L. D. Blaylock Lois James License Renewal Project Manager (Safety)

One White Flint North (MS 011-F1) City of Austin U.S. Nuclear Regulatory Commission Elaina Ball Washington, DC 20555-0001 John Wester Tam Tran Texas Dept. of State Health Services.

License Renewal Project Manager Helen Watkins (Environmental) Robert Free One White Flint North (MS 011 F01)

U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

NOC-AE-16003425 Enclosure Comments Regarding the Safety Evaluation Report (SER) with Open Items Dated October 2016 Related to the License Renewal of South Texas Project, Units 1 and 2

NOC-AE-16003425 Enclosure Page 1of6 Comments Regarding the Safety Evaluation Report (SER) with Open Items Dated October 2016 Related to the License Renewal of South Texas Project, Units 1 and 2 No. SER Location Comment Suggested Resolution Section Page (suggested text is shown by underlining/strikethrough formatting) 1 1.4 1-12 In Table 1.4-1, Current Interim Staff SER Section Guidance Item "Wall Thinning Due to 3.0.3.2.10 Erosion Mechanisms" 3.0.3.2.4 3.0.3.2.6 The SER Section listed 3.0.3.2.10 should be 3.0.3.2.4 and 3.0.3.2.6 2 1.4 1-13 In Table 1.4-1, "Aging Management SER Section of Loss of Coating or Lining Integrity 3.0.3.2.6 for Internal Coating/Linings on In- 3.0.3.2.10 Scope Piping, Piping Components, 3.0.3.2.18 Heat Exchangers and Tanks" Add SER Sections 3.0.3.2.6 and 3.0.3.2.18 3 3.0.3.2.10 3-86 Item (d) second paragraph, the The staff finds the applicant's response acceptable reference to the AMP should be AMP because the acceptance criteria for degraded coatings Xl.M42 as modified by LR-ISG-2013- now includes all the aging mechanisms recommended 01 in AMP Xl.M42 Xl.M27, as modified by LR-ISG-2013-Q1 LR ISG 2012 012, and repairing the coatings based on any indication of the mechanisms helps ensure that degraded coatings are repaired prior to potentially affecting the component's or downstream component's intended function.

' '

>

4 3.1.2 3-265 Table 3.1-1 (3.1.1.22) does not show See STPNOC Letter NOC-AE-15003270 dated June the changes made to the Reactor 30, 2015. (ML15197A029)

(Rx) vessel internals AMP response 1' in NOC-AE-15003270.

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NOC-AE-16003425 Enclosure Page 2 of 6 No. SER Location Comment Suggested Resolution Section Page (suggested text is shown by underlining/strikethrough formatting}

5 3.1.2 3-266 Table 3.1-1 (3.1.1.27) does not show See STPNOC Letter NOC-AE-15003270 dated June the changes made to the Rx vessel 30, 2015. (ML15197A029) internals AMP response in NOC-AE-15003270.

6 3.1.2 3-267 Table 3.1-1 (3.1.1.30) does not show See STPNOC Letter NOC-AE-15003270 dated June the changes made to the Rx vessel 30, 2015. (ML15197A029) internals AMP response in NOC-AE-15003270.

7 3.1.2 3-268 Table 3.1-1 (3.1.1.33) does not show See STPNOC Letter NOC-AE-15003270 dated June the changes made to the Rx vessel 30, 2015. (ML15197A029) internals AMP response in NOC-AE-15003270.

8 3.1.2 3-269 Table 3.1-1 (3.1.1.37) does not show See STPNOC Letter NOC-AE-15003270 dated June the changes made to the Rx vessel 30, 2015. (ML15197A029) internals AMP response in NOC-AE-15003270.

9 3.1.2 3-273 Table 3.1-1 (3.1.1.60) does not show See STPNOC Letter NOC-AE-15003270 dated June the changes made to the Rx vessel 30, 2015. (ML15197A029) internals AMP response in NOC-AE-15003270.

10 3.1.2 3-273 Table 3.1-1 (3.1.1.63) does not show See STPNOC Letter NOC-AE-15003270 dated June the changes made to the Rx vessel 30, 2015. (ML15197A029) internals AMP response in NOC-AE-15003270.

11 3.1.2 3-277 Table 3.1-1 (3.1.1.80) does not show See STPNOC Letter NOC-AE-15003270 dated June the changes made to the Rx vessel 30, 2015. (ML15197A029) internals AMP response in NOC-AE-15003270.

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NOC-AE-16003425 Enclosure Page 3 of 6 No. SER Location Comment Suggested Resolution Section Page (suggested text is shown by underl ini ng/strikethroug h formatti na) 12 3.1.1 3-264 Table 3.1.1 (3.1.1.16) is applicable to Revise Staff Evaluation Column to read STP for loss of material due to general, pitting and crevice corrosion Consistent with NUREG-1801. See further evaluation of carbon steel. See AMR table in Section 3.1.2.2.2.4.

3.1.2.4. Since STP has Model Delta 94 steam generators the additional inspections for Westinghouse Model 44 and 51 steam generators are not applicable as stated in LRA Section 3.1.2.2.2.4.

13 3.1.1 3-272 Table 3.1.1 (3.1.1.57) is not Revise Staff Evaluation Column to read applicable to STP. STP does not have any CASS that is susceptible to Not am;~licable to STP (see SER Section 3.1.2.1.6}.

thermal aging embrittlement. See SER Section 3.1.2.1.6.

14 4.1.2.1.2 4-7 The SER section listed in the third The staff's evaluation of the applicant's AMP 82.1.27 paragraph last sentence on page 4-7 is provided in SER should be 3.0.3.2.22. Section 3.0.3.1.9 3.0.3.2.22.

15 4.4.2 4-107 The SER section listed in the first On the basis of the AMP audit and as documented in paragraph on page 4-107 should be SER Section 3.0.3.1.8 3.0.3.1.7, "Environmental 3.0.3.1.7. Qualification (EQ) of Electrical Components," the staff finds that the EQ Program is consistent with the GALL Report. The staff further concludes that the applicant's EQ of Electrical Equipment TLAA is implemented per the requirements in 10CFR54.21 (c)(1 )(iii).

... , "

16 4.5.2 4-109 The SER section listed in the fourth The staff's review of the Concrete Containment paragraph last sentence on page 4~ Tendon Prestress Program is discussed in SER 109 shoulq pe 3.0.3.1.8. Section 3".0.3.1.9 3.0.3.1.8.

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NOC-AE-16003425 Enclosure Page 4of6 No. SER Location Comment Suggested Resolution Section Page (suggested text is shown by underlining/strikethrough formatting) 17 4.5.2 4-111 The SER section listed in the second The results of the review are documented in the staff paragraph last sentence on page 4- evaluation of the Concrete Containment Tendon 111 should be 3.0.3.1.8. Prestress ProQram in SER Section :3.G.3.1.9 3.0.3.1.8.

18 4.5.2 4-112 The SER section listed in the second This issue is discussed further in SER Section paragraph on page 4-112 should be 3.G.3.1.9 3.0.3.1.8, "Concrete Containment Prestress."

3.0.3.1.8.

19 Appendix A A-2 The text "No later than the date the See STPNOC Letter NOC-AE-15003303 dated Item No 4 renewed operating license November 12, 2015. (ML15334A354 is issued" goes with commitment "Enhance the Open-Cycle Cooling Water System program procedures to:"

20 Appendix A A-3 Revise (NOS) to (NCS). Require coating inspections and tests be performed by Item No 4 a qualified Nuclear Coating Specialist (NCS NGS) as defined by ASTM 07108 endorsed in RG 1.54.

21 Appendix A A-9 Remove the added text "(procedures, Enhance plant specifications !QjpFOeeEl1:1Fes, Item No 13 inspections, or other, as appropriate) inspeetions, OF otheF, as appFOpFiate) by doing the by doing the following". This text was follmving:

not in the LRA or referenced letters.

22 Appendix A A-10 Remove the following duplicate bullet Use of excessive cathodic protection polarized Item No 13 "Use of excessive cathodic protection potential on coated piping should be avoided. The polarized potential on coated piping limiting critical potential should not be more negative should be avoided. The limiting than 1200 mV relative to a copper/copper sulfate critical potential should not be more reference electrode (CSE).

negative than 1200 mV relative to a copper/copper sulfate reference Use of exeessive eathodie pFOteetion polaFized electrode (CSE)." -- potential on eoated piping sho1:1ld be avoided. +he limiting 6Fitieal potential sho1:1ld not be moFe negative

. than 12GG mV rnlative to a CSE.

.  :

NOC-AE-16003425 Enclosure Page 5 of 6 23 Appendix A A-12 Fix the formatting of the second

• Specify that Category E inspections be used when Item No 13 bulleted item. See STPNOC Letter the cathodic protection system has been installed NOC-AE-16003385 dated June 28, but the portions of the piping covered by that 2016. (ML16190A135) system fail to meet the acceptance criteria.

Category E inspections are 5 percent, NTE 5. The following condition must be present.

0 Coatings and backfill are provided in accordance with STP backfill specification.

0 There have been no leaks in buried piping due to external corrosion and no significant coating degradation or metal loss in more than 10 percent of inspections conducted.

0 Soil has been demonstrated to be not corrosive for the material type using the following.

• A minimum of three sets of soil samples will be obtained in the vicinity where the cathodic protection system fails to meet the acceptance criteria.

• The soil will be tested for soil resistivity, corrosion accelerating bacteria, pH, moisture, chlorides, sulfates, and redox potential.

• The potential soil corrosivity will be determined for each material type of buried in-scoQe QiQing in the vicinity of the failed cathodic Qrotection system. In addition to evaluating each individual Qarameter, the overall soil corrosivity will be determined.

• If Qortions of the installed cathodic Qrotection system fail to meet the acceQtance criteria, soil testing will be conducted at a minimum of once in each 10-year Qeriod starting at the time when it was determined that the cathodic Qrotection svstem failed to meet the acceotance.

NOC-AE-16003425 Enclosure Page 6 of 6 No. SER Location Comment Suggested Resolution Section Page (suggested text is shown by underlining/strikethrough formattinal 24 Appendix A A-25 Revise Item 39 per STPNOC Letter Enhance the Selective Leaching of Aluminum Bronze Item No 39 NOC-AE-16003394 dated July 28, procedures to:

2016. (ML16221A391)

• Visually examine aluminum bronze materials exposed during inspection of the buried essential cooling water piping for evidence of leaka§e coating degradation and

• If degradation is identified near a weld a volumetric examination will be gerformed to determine if cracking of the weld is occurring.

• If a leak from buried aluminum bronze welds is discovered by surface water monitoring or during a buried ECW piping inspection, a section of each leaking weld will be removed for destructive metallurQical examination.