ML20135G586
| ML20135G586 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse, Oconee, 05000000 |
| Issue date: | 09/11/1985 |
| From: | Linn M BABCOCK & WILCOX OPERATING PLANTS OWNERS GROUP |
| To: | Vissing G NRC |
| Shared Package | |
| ML20135G587 | List: |
| References | |
| TAC-44335, NUDOCS 8509190473 | |
| Download: ML20135G586 (4) | |
Text
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1 n10WNERS GROUP i_O_ r 1 % *%
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g ggn m Working Together to Economically Provide Reliable and Safe Electrical Power Suite 220 September 11, 1985 7910 Woodmont Avenue Bethesda, Maryland 20814 (301)951 3344 Mr. G.
C. Vissing U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
B&W Owners Group Emergency Operating Procedures Technical Bases Document, B&W Document No. 74-1152414-00 References.
- 1) Whitney, D.
D.,
"B&W Owners Group' Plan and Schedule for Addressing the Safety Evaluation of
' Abnormal Transient operating Guidelines',"
letter from D.
D. Whitney to D. G.
- Eisenhut, December 9, 1983.
- 2) Eisenhut, D.
G.,
" Safety Evaluation of ' Abnormal Transient Operating Guidelines' (Generic Letter 83-31)," letter from D.
G.
Eisenhut to All Operating Reactor Licensees, Applicants for an Operating License, and Holders of Construction Permits for Babcock & Wilcox Pressurized Water Reactors, September 19, 1983.
Dear Mr. Vissing:
Reference 1 described the B&W Owners' plan and schedule for addressing the items identified in the Safety Evaluation Report (Reference 2) written for the Oconee Nuclear Station Unit 3 (ONS-3) Abnormal Transient Operating Guidelines (ATOG).
l A major portion of this plan (Reference 1) was to develop a 1
document that consolidated the ATOG technical bases, the supple-l mental material provided in response to NRC questions for the l
ONS-3 final ATOG, and the most current information developed from l
other B&W Owners Group programs.
This document entitled, "B&W Owners Group Emergency Operating Procedures Technical Bases Document," (TBD) is complete and five copies are provided as enclosures to this letter.
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B509190473 050911 hDR ADOCK 05000287 PDR
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e In addition, many of the Reference 2 open issues were identified by. Reference 1 to be addressed by the TBD.
The following Reference 1 paragraphs have been addressed by the TBD:
Reference 1 Issue Paracraoh (Reference 2 Section Number)
Comments 3.1 SG Overfill (3.6.2)
Generic portions j
complete.
i 3.2 RCS Depressurization Alter-Analytical and natives (3.7.2) generic portions complete.
3.3 Multiple Tube Ruptures (3.7.2)
Complete.
3.4 Multiple Tube Ruptures SG All non-IST por-Inventory control (3.7.2) tions complete.
1 i
3.5 Loss of LPI Sump Recircula-Complete.
j tion (3.1.2) 3.7
. Containment (3.3.2, 3.10.2, Generic portions a
3.12) complete.
3.8 RCS Voids (3.4.2)
Generic and non-1 IST portions j
complete.
3.9 PORV Depressurization (3.7.2)
Complete.
3.10 Cyclic Boiler-Condenser All non-IST por-l Phenomena (3.13) tions complete.
3.13 HPI Cooling with Inoperable Complete.
PORV (3.9.4.2) 3.14 Solid Plant Cooldown (3.9.5.2)
Complete.
3.15 Plant Cooldown Procedures Generic portions Structure and Interface complete.
(3.2.2, 3.9.6) i 3.16 DHRS Operation with a Satura-Complete.
tad RCS _ (3.9.4. 2) 3.17 Extended Coverage of Entry Generic portions Conditions (3.2.2, 3.11) complete.
i 3.18 Loss of AC Power (3.3.2, Generic portions l
3.12, 3.13)
Complete
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5 i
i Reference 1 Issue j
Paracraoh (Reference 2 Section Number)
Comments 3.19 ATWS (3.3.2, 3.12)
Complete.
l
-3.20 PTS (3.4.2, 3.9.4.2)
Generic portions.
complete.
3.21 Post ICC with Core Damage SGTR portion (3.7.2, 3.8.2) complete.
3.22 RCP Operations (3.3.2, 3.5.2, Complete.
I 3.6.2, 3.7.2, 3.8.2, 3.9.6, 3.13) 3.23 RCP Restart with Voids All non-IST com-(3.5.1, 3.8.2, 3.13) plate.
3.25 Statement Clarification Complete.
(4.2.12) i i
3.25 EFW to Isolated SG (4.2.13)
Complete.
3.25 Statement Clarification Complete.
l (4.2.15) l 3.25 Use of PORV (4.2.16)
Complete.
3.25 ATOG Inconsistencies (4.2.17)
Complete.
3.25 SG Inventory Control Incon-
- Complete, sistencies (4.2.18) l l
3.15 Special ICC Precautions Generic portions j
(4.2.21) complete.
l 3.25 Term Clarification (4.2.25)
Complete.
3.25 Time Frame Quantification complete.
(4.2.26) 3.25 Post LOCA Time Frame Justifi-Complete.-
cation (4.2.27) 3.25 ICC Indication Clarification Complete.
l (4.2.28) l By submittal of the attached TBD the B&W Owners Group's obliga-I tion for addressing the following items from above is complete; 3.1, 3.2, 3.3, 3.5, 3.7, 3.9, 3.13, 3.14, 3.15, 3.16, 3.17, 3.18, 3.19, 3.20, 3.22, and 3. 25.
In addition, those portions of the l
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following issues not tied to the IST or IDCOR programs are complete; 3.4, 3.8, 3.10, 3.21, and 3.23.
These issues related to the IST and IDCOR programs will be addressed by later revi-sions of the TBD as described in Reference 1.
With respnct to the Toledo Edison Company's Davis-Besse plant, the method of cooling the core using HPI/MU cooling described in the TBD may be subject to change based on the results of an ongoing analysis program for Davis-Besse which could not be factored into the TBD to meet the submittal schedule.
It is not known at this time if the changes to the TBD will be necessary as a result of this analysis program.
The need for a review of the TBD will be examined at the completion of the program.
Very truly yours, M44.
M. A. Linn Chairman B&WOG Operator Support Committee l
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