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| | number = ML090690432 | | | number = ML090690432 |
| | issue date = 11/04/2008 | | | issue date = 11/04/2008 |
| | title = Diablo Canyon Power Plant, Unit Nos.1 and 2 - Email Request for Additional Information Re License Amendment Request (TAC Nos. MD8471 and MD8472) | | | title = Unit Nos.1 and 2 - Email Request for Additional Information Re License Amendment Request (TAC Nos. MD8471 and MD8472) |
| | author name = Wang A B | | | author name = Wang A B |
| | author affiliation = NRC/NRR/DORL/LPLIV | | | author affiliation = NRC/NRR/DORL/LPLIV |
Revision as of 03:41, 17 April 2019
Letter Sequence RAI |
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MONTHYEARML0810102072008-04-0303 April 2008
Diablo Canon, Units 1 & 2 - License Amendment Request 08-02, Revision to Technical Specification 3.7.5, Auxiliary Feedwater System and 3.7.6 Condensate Storage Tank and Fire Water Storage Tank
Project stage: Request
ML0815405402008-06-0404 June 2008
Amendments Auxiliary Feedwater and Condensate Storage Tanks (TACs MD8471 and MD8472)
Project stage: Other
DCL-08-023, Supplement to License Amendment Request 08-02, Revision to Technical Specifications 3.7.5, Auxiliary Feedwater System, and 3.7.6, Condensate Storage Tank and Fire Water Storage Tank2008-06-20020 June 2008
Supplement to License Amendment Request 08-02, Revision to Technical Specifications 3.7.5, Auxiliary Feedwater System, and 3.7.6, Condensate Storage Tank and Fire Water Storage Tank
Project stage: Supplement
ML0825404362008-07-24024 July 2008
Email Sending Request for Additional Information, Revise TS 3.7.5, Auxiliary Feedwater System and 3.7.6, Condensate Storage Tank and Fire Water Storage Tank
Project stage: RAI
ML0825404962008-07-24024 July 2008
Draft Diablo Canyon, Units 1 and 2, Request for Additional Information, Revise TS 3.7.5, Auxiliary Feedwater System and 3.7.6, Condensate Storage Tank and Fire Water Storage Tank
Project stage: Draft RAI
ML0820407482008-08-0101 August 2008
Acceptance Review of Proposed Amendments Revision to Technical Specifications 3.7.5, Auxiliary Feedwater System, & 3.7.6, Condensate Storage Tank & Fire Water Storage Tank (Tac Nos. MD8471 and MD8472)
Project stage: Acceptance Review
ML0828314432008-09-21021 September 2008
CST RAIs (Email)
Project stage: RAI
ML0826702672008-09-21021 September 2008
Request for Additional Information on Condensate Storage Tank Level Amendment
Project stage: RAI
DCL-08-081, Response to Request for Additional Information, License Amendment Request 08-02, Revision to Technical Specifications 3.7.5, Auxiliary Feedwater System, and 3.7.6, Condensate Storage Tank and Fire Water Storage Tank2008-10-0101 October 2008
Response to Request for Additional Information, License Amendment Request 08-02, Revision to Technical Specifications 3.7.5, Auxiliary Feedwater System, and 3.7.6, Condensate Storage Tank and Fire Water Storage Tank
Project stage: Response to RAI
ML0906904322008-11-0404 November 2008
Unit Nos.1 and 2 - Email Request for Additional Information Re License Amendment Request
Project stage: RAI
DCL-08-093, Response to NRC Request for Additional Information Regarding License Amendment Request 08-02, Revision to Technical Specifications 3.7.5, Auxiliary Feedwater System, and 3.7.6, Condensate Storage Tank and Fire Water2008-11-0606 November 2008
Response to NRC Request for Additional Information Regarding License Amendment Request 08-02, Revision to Technical Specifications 3.7.5, Auxiliary Feedwater System, and 3.7.6, Condensate Storage Tank and Fire Water
Project stage: Response to RAI
ML0906902942008-11-21021 November 2008
Meeting Slide, Spectra 6.5 Slide from Pacific Gas and Electric Regarding License Amendment Request Re AFW System and CST, Diablo Canyon Power Plant, Unit Nos. 1 and 2
Project stage: Meeting
ML0906902422008-11-21021 November 2008
Email from Pacific Gas and Electric Regarding Spectra 6.5 Slide, License Amendment Request Re AFW System and CST
Project stage: Request
DCL-08-106, Response to NRC RAI Regarding License Amendment Request 08-02, Revision to Technical Specifications 3.7.5, Auxiliary Feedwater System, and 3.7.6, Condensate Storage Tank and Fire Water Storage Tank2008-12-16016 December 2008
Response to NRC RAI Regarding License Amendment Request 08-02, Revision to Technical Specifications 3.7.5, Auxiliary Feedwater System, and 3.7.6, Condensate Storage Tank and Fire Water Storage Tank
Project stage: Response to RAI
ML0906308082009-03-30030 March 2009
Issuance of Amendment Nos. 204 and 205, Revise TS 3.7.5, Auxiliary Feedwater (AFW) System, and TS 3.7.6, Condensate Storage Tank (CST) and Fire Water Storage Tank (Fwst)
Project stage: Approval
2008-04-03
[Table View] |
Text
From: Alan Wang Sent: Tuesday, November 04, 2008 9:49 AM To: Ken Schrader
Subject:
Additional Question onCST Ken, here it is:
- 1. In the supplemental letter provided from Westinghouse, dated June 16, 2008, it is stated that "the assumed level restoration [of the steam generator water level] was reduced from no load programmed level to the narrow range lower level tap." As depicted in Figure 5.5-4 of the DCPP UFSAR, "Westinghouse Delta 54 Replacement Steam Generator," the narrow range lower level tap is positioned below the top of the steam generator U-tubes. This restoration level was used as the basis for the requested TS limit of 200,000 gallons in the CST.
It has been communicated that in the case of the limiting scenario (LOOP with natural circulation cooldown at reduced rate) the EOP would instruct operators to maintain steam generator water level between 20% and 60%, which is above the top of the U-tubes, during the entire cooldown. This is possible due to the fact that the CST upgrade was designed to provide approximately 222,600 gallons of seismically-qualified condensate as opposed to the minimum 200,000 gallons. However, after the requested change to the CST TS limit, it is possible for the licensee to legally operate with as little as 200,000 gallons available in the CST. While this volume is sufficient to meet the cooling requirements of the postulated event, it would not be enough to maintain steam generator water level between 20% and 60% for the entire duration of the event. This means that some portion of the steam generator U-tubes would become uncovered during the 8-hour cooldown.
The NRC staff requests confirmation that the radiological release due to the postulated LOOP with natural circulation cooldown at a reduced rate remains bounded by more severe accident analyses. This confirmation should assume maximum allowable primary activity levels for normal operation and maximum allowable primary to secondary leakage for normal operation, and assume a leakage point at or near the top of the U-tube bundle.
E-mail Properties Mail Envelope Properties (419623E8C7444444BF132DA3AE69EDA2106B64D345)
Subject:
Additional Question onCST
Sent Date: 11/4/2008 9:48:32 AM Received Date: 11/4/2008 9:48:00 AM From: Alan Wang
Created By: Alan.Wang@nrc.gov
Recipients:
KJSe@pge.com (Ken Schrader)
Tracking Status: None
Post Office:
HQCLSTR02.nrc.gov
Files Size Date & Time
MESSAGE 8086 11/4/2008
Options Expiration Date:
Priority: olImportanceNormal ReplyRequested: False Return Notification: False
Sensitivity: olNormal Recipients received:
