ML083150942
| ML083150942 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 11/06/2008 |
| From: | NRC/RGN-III |
| To: | Exelon Generation Co |
| References | |
| Download: ML083150942 (3) | |
Text
Braidwood IP 71152 - Information Request - November 6, 2008 Part A. Please send a copy of the following documents and supporting documents to the Region III Office in Lisle IL by December 5, 2008, to support preparation for an on-site NRC baseline inspection in accordance with IP-71152 Identification and Resolution of Problems. If possible, provide these documents in electronic format (e.g. E-mail or CD-Rom preferred). Please contact Gerry O'Dwyer (630) 829-9624 or Mel Holmberg - (630) 829-9748 for any questions.
Request Doc Type Subject Supporting Documents No.
Braidwood Corrective Actions 1 Corrective Any ARs other than those identified CAs with due dates, Action above which have been issued since apparent/root causes as Records May 1, 2007, associated with the HUT applicable and/or piping components which discharge into the HUT.
3 Corrective Provide ARs associated with calculation CAs with due dates, Action CN-CRA-00-47 which contained apparent/root causes as Records assumptions for HUT level which were applicable not consistent with plant operations (e.g.
80 percent full).
3 Corrective Provide ARs associated with a recent CAs with due dates, Action NRC inspection finding identified at apparent/root causes as Records Byron associated with failure to update applicable.
the Byron/Braidwood UFSAR for the Boron Recycle and RH Systems.
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Part B. Please provide a copy of the following documents to the onsite review location or the Braidwood Resident Office by December 15, 2008, to support on-site NRC reviews in accordance with IP-71152 Identification and Resolution of Problems."
Request Subject No.
Information Associated with Calculations CN-CRA-08-9 and CN-CRA-07-50 associated with the boric acid holdup tank (HUT) tank response to opening of the RHR suction pipe relief valve.
1 Latest revision of Calculations CN-CRA-08-9 and CN-CRA-07-50, with Braidwood Station review and acceptance documentation and any other supporting or related calculations.
2 Was CN-CRA-08-09 site accepted and approved as a Braidwood design basis calculation? If not, explain.
3 During shutdown cooling with two RHR systems in operation, the potential exists for two RHR train suction relief valves (and possibly two pump discharge relief valves) to discharge simultaneously to the HUT. Provide the analysis which identifies the effect of multiple relief valves discharging into the HUT. If no analysis exists, explain why this is not required or identify planned corrective actions.
4 Calculations CN-CRA-07-50 and CN-CRA-08-09 do not address the effect of exceeding 200 F (design basis for HUT - UFSAR 15.7.2.1). Provide the analysis which evaluates the effect on the HUT when exceeding 200F at any location within the HUT. If no analysis exists, identify planned corrective actions.
5 Calculations CN-CRA-07-50 and CN-CRA-08-09 identify scenarios where the HUT and/or connected piping runs will exceed the design Code temperature (e.g. 200 F) and pressure ratings (e.g. 30 psig - pipe runs to HUT or 15 psig - HUT). Identify the corrective actions which preclude the scenarios which exceed these design conditions.
6 Conversion table or formula used for the HUT level with respect to each tank level location referenced in calculations CN-CRA-08-9 and CN-CRA-07-50 (e.g. Tank level as a percent of tank volume with respect to inlet pipes or other referenced locations expressed as inches above tank bottom and/or inches above inlet pipe).
Other Documents and Requests 7 Normal valve lineup for the HUT including the portion of piping systems discharging to the HUT.
8 Normal, abnormal and emergency/ off-normal operating procedures for the HUT.
9 Identify pending or planned procedure changes associated with operation of the HUT or RH systems.
10 Identify any pending or planned design changes associated with the HUT.
11 Identify any RH system or boron recycle system (with respect to HUTs) operating procedure guidance which is unique to Braidwood (e.g. not the same as Byron) and which could potentially impact on the supporting HUT analysis conclusion (e.g. CN-CRA-08-9).
For example, Braidwood RH procedures allow placing a second RH train in service at a higher plant operating temperature than at Byron Station, thus this operating procedure difference should be on the list.
For any procedures differences identified which potential impact the evaluation documented in calculation CN-CRA-08-9 (HUT response to a single RH suction relief blowdown), identify the basis for considering the scenario or conclusions of calculation CN-CRA-08-9 applicable and bounding for Braidwood Station (e.g. two trains of RH relief valves could discharge at higher temperatures at Braidwood than at Byron).
12 Provide a copy of RH system procedures which require minimum quench volumes be established in the HUTs prior to system operation and RH system procedures used to place system in cooldown or to support ECCS operations.
13 Provide copy of the procedure(s) which require and control the equipment status tags on 2
the inlet isolation valves to the HUTs.
14 Identify procedure guidance for alignment of the HUTs to support RH operation.
Specifically, identify if more than one HUT can be aligned to receive RH system relief valve discharges.
15 P&ID Drawings, Safety Injection and RH Systems, (D size).
16 P&ID drawings showing HUT and all attached piping back to systems which discharge into the HUT(D size).
17 Elevation/Isometric drawings of HUT and all attached piping back to systems which discharge into the HUT (D size) 18 Fabrication drawings for HUT (D size) 19 Identify any Braidwood specific design aspects (e.g. different construction codes, or fabrication standards, or piping configurations impacting water hammer susceptibility, or tank configurations impacting quench volumes) applicable to the HUTs or HUT inlet pipe which differs from than that used at Byron Station.
20 Design Specification(s) for HUT and for all piping which discharges into the HUT.
21 For the installed Residual Heat Removal (RHR) suction and discharge relief valves, Provide:
a) the design specification.
b) the document which establishes the design basis relief valve capacity, temperature range and setpoint.
22 For the installed RHR suction and discharge relief valves, the CVCS suction relief valves, and the SI suction relief valves. Identify a) the limiting design basis system transient for each of these relief valves (e.g. that limiting transient which valves are required to pass their maximum capacity and to prevent overpressure) and the source of the design basis transient (e.g. UFSAR Section, TS or Design Specification).
b) if any potential system transients can exist, which would result in more than one of these relief valves lifting at the same time (e.g. a specific pressure induced transient while in solid plant operation in Mode 3 or 4 with RHR inservice).
23 Copy of the applicable Edition and Addenda of the design Code for the HUT (e.g. ASME Code Section III).
24 Identify the applicable design Code for each piping input run which discharge into the HUT and provide a copy of the applicable Edition and Addenda of the design Code for these piping runs.
25 Identify significant loop seal pipe configurations in the HUT inlet pipe which are subject to potential water hammer transients. Identify if any of these loop seal configurations are unique to Braidwood (e.g. not similar to Byron).
26 Identify any water hammer evaluations for the HUT inlet pipe. If no water hammer evaluations exist, identify basis for current operability and provide a copy of this document.
27 Provide the RHR system relief valve vendor manuals.
28 Provide access to a copy of the current UFSAR, TS and TRM at on-site review location.
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