ML20247H296
| ML20247H296 | |
| Person / Time | |
|---|---|
| Issue date: | 07/21/1989 |
| From: | Rossi C Office of Nuclear Reactor Regulation |
| To: | Wilgus W BABCOCK & WILCOX OPERATING PLANTS OWNERS GROUP |
| References | |
| NUDOCS 8907280345 | |
| Download: ML20247H296 (5) | |
Text
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o UNITED STATES 6 NUCLEAR REGULATORY COMMISSION
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f July 21,1989 L
l'r. Walter S. Wilgus, Chairman The-B&W Owners Group
> Suite 525 1700 Rockville Pike Rockville,t'arylanj 2085; Cear Mr. Wilcus:
As you know, the Babcock & Wilcox Owners Group (B&WOG) submitted proposed Revised Standard Technical Specifications (RSTS) to the NRC staff on May 1, 1989. On May 15. the B&WCG met with the staff to describe the content and organization of the proposed RSTS and supporting material submitted for review. The NRC staff conducted an acceptance review of the' proposed RSTS from May 15 to May 3C and met with the B&WOG on June 12 to inform them of the results of the acceptance review.
As a result of the acceptance review and the Oure 12 meeting, the staff accepted the proposed RSTS for detailed review. However, it is important to emphasize that the staff found numerous, significant deficiencies in the proposed RSTS and that the key to our acceptance of the RSTS for detailed review was the expressed willingness of the B&WOG to cooperate with the staff and to supply in a timely '
manner information needed for the detailed review.
The ultimate impact of what appears to be significant departures from our original ground rules for the development of the new STS will depend on the adequacy and timeliness of the B&WOG's response to the items listed below.
Therefore, while we are beginning our detailed review, we will reassess our position by October 1989 to determine if it is necessary to readjust the schedule i due to a lack of the required information.
l B&WOG ACT10t PEQUIRED lt ORDER TO FULLY PROGRESS WITH THE DETAILED REVI 1hE PROPOSED B&WOG RSTS A. Provide justification for technical changes from existing requirements; '
e.g., extension of completion times for Accident Ponitoring Instrumen-I tation from 7 to 30 days. Justification cannot just be a plant specific example (e.g., CR 3 or Oconee PRA) or engineering judgement without supporting data or analyses. ,
B. Include in the RSTS all Limiting Conditions for Operation (LCOs) and ,
Surveillance Requirements (SRs) required by the "NRC Staff feview of the Owners Croups' Application of the Interim Policy Staten.ent Criterie" (i.e., the " Split Report"). The following are sore examples of LCOs identified by the staff during the acceptance review that need to be included: .
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Mr. Walter S. Wilgus ,
- 1. Remote shutdown instrumentation. (STS 3.3.3.5)
- 3. Xenon reactivity (STS 3.1.3.9). However, it may be possible to justify removing this LC0 on a plant specific basis.
4.. Decay heat removal (DHR), cold shutdown (STS 3.4.1.4).
- 5. All engineered safety features actuation system (ESFAS) instrumentation specifications (STS 3.3.2 Table 3.3-3).
- 6. Radiation Monitoring Instrumentation including the criticality monitor (STS 3.3.3, Table 3.3-6).
7.
instruments and provision for All Category 1 accident plant specific Type A instruments monitoring (RSTS 3.2.37. Table 3.2-1). See attached list.
C. Identify the location of all requirements to be relocated within RSTS; e.g., Radiation Monitoring Instrumentation, Table 3.3-6.
D. Include tendon surveillance for pre-stressed, reinforced concrete containments and steam generator tube surveillance in RSTS.
E. Please review all RSTS references to a core operating limits report (COLR) to make sure they are in harmony with Generic letter 88-16 and the guidance provided in our letter to R. A. Newton, April-28, 1989, concerning the proposed Westinghouse Owners Group (WOG)'STS, as discussed .in the June
- 29. 1989 n,eeting between the B&WOG and the staff. With respect to the B&WOG's proposed RSTS, the staff position is that the following parameters should not be relocated to a COLE. Therefore, the B&WOG should provide complete technical specifications for these parameters,
- a. Limiting Safety System Settings
- b. LC0 3.2.4 Quadrant Power Tilt
- c. LC0 3.3.1, Reactor Protection System trip setpoint
- d. LC0 3.2.2. Nuclear Hot Channel Factor
- e. LCO 3.2.3, Nuclear Enthalpy Rise hot channel factor The tioderator Temperature coefficient (MTC) may be relocated to a COLR. but
'the positive and negative bounds should be retained in RSTS.
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F Mr.l Walter.S. Wilgus Finally, provide a sample COLR that shows the inform 6 tion which is to be relocated from the RSTS.
Consistent with the June 12 meeting, your complete response should be to the staff by July 31, 1989.
Sincerely.
l<j
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Charles E. Rossi, Director Division of Operational Events Assessment Office of Nuclear Reactor Regulation Attachments:
List of Attendees for June 12. 1989 Meeting List of Category 1 Accident Monitoring Instruments DISTRIBUTION:
OT5B R/F DOEA R/F mLCentralsFijes CERossi JACalvo RLEmch FJMiraglia .CHBerlinger CJHaughney FMReinhart JZwolinski GMHolahan.
FJCongel SAVarga JRichardson JWRoe- WFKane JLieberman-EJButcher PDR OTSB Members STS Review Team Ing C. Arredondo of Mexico LAReyes EGGreenman Ivan Recarte of Spain JMilhoan RZimmerman KARaglin DCB
- SEE PREVIOUS PAGE FOR CONCURRENCE l (LTRWILGUSB&WOGSCHIFFGENS)
- 0TSB:DOEA:NRR J0Schiffgens:pmc
- 0TSB:00EA:NRR FMReinhart
- 0TSB:DOEA:NRR *C:0TSB:D0EA:NRR DCFischer JACalvo jQ osst 07/18/89 07/18/89 07/18/89 07/18/89 07/u/89
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- LIST OF ATTENDEES FOR JUNE 12, 1989 PEETINf1 i
NAME AFFILIATION Mark Reinhart -NRR/0TSB David Fischer NRR/0TSB Larry Phiilips NRR/ DEST /RSXB John Schiffgens NRR/01SE G. C. Schieck B&W/B&WOG Courtney W. Smyth GPUN/B&WOG Dan Green _
FPC/B&WOG Philip J. North 0 UKE /B&WOG Jim tiiller NRR/0TSB Donald R. Hoffman BWROG TSC/ EXCEL P. R. Sgarro PP&L/BWROG R. A. Turner B&W C. F. McPhatter B&W S. Diab' RAB/NEC James Wing NRR/DREP/PRAB Daniel Fieno NRR/SRXB Dennis M. O'Shea FPC/B&WOG Jose Calvo NRR/0TSB Harley Silver NRR/CR-3 PM Joe Joyce NRR/SICB Iqbal Ahmed NRR/ SICS Larry Kopp NRR/SRXS Dan Fieno NRR/SRXB Warren J. Hell fiUMARC
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