ML13298A130

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NRR E-mail Capture - SE Input for Proprietary Review
ML13298A130
Person / Time
Site: Braidwood  Constellation icon.png
Issue date: 10/09/2013
From: Holden L
Exelon Corp
To: Joel Wiebe
Division of Operating Reactor Licensing
References
Download: ML13298A130 (7)


Text

1 NRR-PMDAPEm Resource From:

Leslie.Holden@exeloncorp.com Sent:

Wednesday, October 09, 2013 11:36 AM To:

Wiebe, Joel Cc:

kevin.borton@exeloncorp.com

Subject:

RE: SE Input for Proprietary Review

Joel, As I mentioned in yesterdays e-mail during our review we did notice a couple of items that we would like to offer comments on for your consideration:

Section 2.0 (page 2) the LEFM acronym is for the Leading Edge Flow Meter.

Section 3.1 (page 4) no reference is included for ER-720. Based on information from Cameron, ER-720 is Meter Factor Calculation and Uncertainty Assessment for Harris Nuclear Plant. It is not clear if this should be referring to the Byron and Braidwood Bounding Uncertainty Analyses (Reference N).

Section 3.8.2.2.2, Item (6) (pages 24 and 25) regarding tempering flow EGC offers the following clarifying comment to information provided in the copy of EC 388706, Byron Unit 1 Observation of Upward Trend in Secondary Parameters, (Section 4.6) that was provided during the audit.

As is stated in the SER, tempering flow bypasses the LEFM and the venturis but is accounted for in the calorimetric. However, tempering flow is normally 40,000 lb/hr per loop (i.e., 160,000 lb/hr total based on 4 loops). During our troubleshooting, one tempering line at a time was isolated and correspondingly the LEFM/venturi flow was expected to increase by 40,000 lb/hr. This was validated for loops A. B and C (nearly identical decrease of within <2,000 lb/hr), however, when loop D tempering line flow was isolated, the LEFM/venturi flow increased by 46,000 lb/hr. Since the tempering line flow indication was 41,000 lb/hr before isolation, there was an approximately 5,000 lb/hr difference. Considering that the other three loops performed as expected, the total tempering line flow error of 5,000 lb/hr into a total feedwater flow of 16,000,000 lb/hr results in an error of approximately 0.03% (5,000/16,000,000=0.0003). This error was much smaller than the observed shift in secondary parameters from May to September, 2011 (0.2%-0.3%) and as such it was not considered as a cause of the secondary parameter shift.

The steam generator (SG) blowdown flow is approximately 18,000 lb/hr per loop (i.e., approximately 72,000 lb/hr total based on 4 loops). During our troubleshooting, one SG blowdown line at a time was isolated and correspondingly the LEFM/venturi flow was expected to decrease by 18,000 lb/hr. This was validated for loops A, C, and D (nearly identical increase of within <2,000 lb/hr), however when loop B, the flow through the LEFM and venturi decreased approximately 28,000 lb/hr. Considering the SG blowdown flow indication was 18,500 lb/hr before isolation, there was an approximately 10,000 lb/hr difference. Considering that the other three loops performed as expected, the total error of 10,000 lb/hr into a total feedwater flow of 16,000,000 lb/hr results in an error of approximately 0.063% (10,000/16,000,000=0.00063). Unlike the tempering line flow error, this error has a conservative effect on reactor power and would result in a shift in secondary parameters in the opposite direction than what was observed from May to September, 2011. Therefore, this error was also not considered a cause of the secondary parameter shift.

We have reviewed the draft SER from the Reactor Systems Branch and there is no proprietary information contained within it.

Leslie

2 Leslie E. Holden Senior Regulatory Engineer Power Uprate Cantera Office 4300 Winfield Road Warrenville, IL 60555 Office: 630 657 3316 l Cell: 630 291 7329 l Fax: 630 657 4300 Leslie.Holden@ExelonCorp.com www.ExelonCorp.com From: Holden, Leslie E.:(GenCo-Nuc)

Sent: Tuesday, October 08, 2013 4:51 PM To: 'Wiebe, Joel' Cc: Borton, Kevin F:(GenCo-Nuc)

Subject:

RE: SE Input for Proprietary Review

Joel, We have determined that there is no proprietary information in the draft SER.

We do have a couple of minor comments on the LEFM section for your consideration, but I am waiting on a final ok on the wording from the thermal engineer at Byron (its my fault, I didnt get him the final wording until this afternoon). Ill send them to you on Wednesday as soon as I hear from him.

Leslie Leslie E. Holden Senior Regulatory Engineer Power Uprate Cantera Office 4300 Winfield Road Warrenville, IL 60555 Office: 630 657 3316 l Cell: 630 291 7329 l Fax: 630 657 4300 Leslie.Holden@ExelonCorp.com www.ExelonCorp.com From: Wiebe, Joel [1]

Sent: Monday, September 30, 2013 3:51 PM To: Holden, Leslie E.:(GenCo-Nuc)

Cc: Gullott, David M.:(GenCo-Nuc)

Subject:

SE Input for Proprietary Review Please note that this is not the final SE input, but we would like you and your vendor to review this for proprietary information.

3 This e-mail and any attachments are confidential, may contain legal, professional or other privileged information, and are intended solely for the addressee. If you are not the intended recipient, do not use the information in this e-mail in any way, delete this e-mail and notify the sender. -EXCIP

Hearing Identifier:

NRR_PMDA Email Number:

884 Mail Envelope Properties (D86DC9B638385E4891F7F7D76BA6455D0284597D)

Subject:

RE: SE Input for Proprietary Review Sent Date:

10/9/2013 11:35:53 AM Received Date:

10/9/2013 11:36:00 AM From:

Leslie.Holden@exeloncorp.com Created By:

Leslie.Holden@exeloncorp.com Recipients:

"kevin.borton@exeloncorp.com" <kevin.borton@exeloncorp.com>

Tracking Status: None "Wiebe, Joel" <Joel.Wiebe@nrc.gov>

Tracking Status: None Post Office:

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