ML20080A309
| ML20080A309 | |
| Person / Time | |
|---|---|
| Site: | Perry, River Bend, Clinton, 05000000, 05000447 |
| Issue date: | 07/15/1983 |
| From: | Holtzscher D ILLINOIS POWER CO., LICENSING REVIEW GROUP II |
| To: | Stefano J Office of Nuclear Reactor Regulation |
| References | |
| L17-83(07-15)-6, L17-83(7-15)-6, U-0652, U-652, NUDOCS 8307250367 | |
| Download: ML20080A309 (12) | |
Text
-
U-0652 Illinois Power Company Ll7-s3(07-153-6 500 SOUTH 27TH STREET, P. O. BOX 511. DECATUR, ILLINOIS 62525-1805 July 15, 1983 Mr. John J. Stefano Project Manager Licensing Branch No. 1 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Dear Mr. Stefano:
Licensing Review Group-II Summary Status of Issues Your letter to me dated May 2, 1983 requested that LRG-II provide a summary status of the issues being addressed by the group.
This status is provided in the table attached to this letter.
At the current time, there are four issues in the table which require further LRG-II action prior to NRC close-out and one issue requiring procedural upgrading.
The detailed status on these issues is as follows:
1.
9-RSB; Long-Term Operability of Deep Draft Pumps our position on this issue was provided in Volume V of the Position Papers (May 17, 1982).
A response to this position paper was received via the letter to LRG-II from Mr. T. Novak (NRC) dated May 3, 1983.
This letter indicates that the position paper appears acceptable but requests that we confirm our conformance to the IE approach as detailed in the attachment to Mr. Novak's letter.
We will address our conformance to the IE approach in a revised 9-RSB position paper to be issued in August.
2.
2-CPB; Seismic and LOCA Loads on Fuel Our position on this issue was provided in Volume VI of the Position Papers (September 3, 1982).
Our position is based on our licensing topical report (NEDE-21175-P, Supplement 3, "BWR/6 Fuel Assembly - Evaluation of Combined SSE and LOCA Loads") which is currently under review at the NRC and has been the subject of meetings in January and June between LRG-I/II, GE and NRC.
Generic resolution of this issue will be based on NRC acceptance of the report.
g, A. f{susins sly Ch.qt : a)WDLM=rb"$
H. Ab usoir I
w rau Sktw
- s. we, p RGO7250367 830715 MYM/
4 4
Mr. John J. Stefano U-0652 Page #2 L17-8 3 (07-15 ) -6 3.
1-HFS; Special Low-Power Testing Program This issue was resolved via the LRG-II position in Volume III of the Position Papers (January 25, 1982).
One of the commitments in this position paper required the evaluation of the simulated loss of A/C power tests at newly licensed BWRs and the performance of such a test, if required by the NRC.
Generic Letter 83 - 24 dated June 29, 1983 revises this requirement by requesting an evaluation of the impact of such testing on equipment.
LRG-II shall revise the generic position paper in response to NRC Generic letter 83-24.
4.
4-MEB; Kuo Sheng Incore Instrument Tube Break Our position on this issue was provided in Volume VI of the Position Papers (September 3, 1982).
The position paper endorses the strengthening of instrument tubes, modifying operating procedures and installing a flow deflector.
This approach was similar to that found acceptable on the Grand Gulf Project.
Subsequent testing of the deflector design at GE indicated fatigue damage of the LPCI thermal shield.
The need to re-evaluate the modification and provide a revised design was addressed in the letter to LRG-II from Mr.
B. J. Youngblood (NRC) dated May 26, 1983.
We will address the revised " design" of the modifications in a revised 4-MEB position paper to be issued in August.
5.
3-CHEB; Post-Accident Sampling Core Damage Estimate our position on this issue was provided in Volume VI of the Position Papers (September 3, 1982).
The core damage estimate method was found acceptable on an interim basis in the Clinton SSER #2 (Section 9.3.5.2).
Total acceptance of the method will require the incorporation of parameters independent of radiochemical analysis into the procedure.
We shall address the incorporation of such parameters into the procedure in a revised 3-CHEB position paper.
In addition to future action on three of the above issues, we are currently investigating other potential generic issues.
If other issues are found and are amenable for group action, we will notify you.
4 Mr. John J. Stefano U-0652 Page'#3 L17-8 3 (07-15 ) -6 We appreciated the opportunity to meet with you during our June 9 meeting and look forward to future discussions with you as the new LRG-II Project Manager.
Sincerely, h./
D. L. Holtzscher Chairman LRG-II Working Group DLH/em/LETl
Attachment:
Status of LRG-II Issues cc:
B. J. Youngblood, Chief Licensing Branch No. 1, NRR E. M. Buzzell', CEI W. J. Reed, GSU R. Artigas', GE R.
S. Boyd, KMC J. D. Richardson, MP&L J. Palomo, Hydroelectrica Espanola P. Powell, WPPSS 1
y
.v-.
c 4,
,- c ---- -- - -..
Pagt 1 of 9 STATUS OF LRG-II ISSUES PLANT-SPECIFIC ISSUE SUBMITTAL ENDORSEMENT DOCUMENTED NUItBER TITLE DATE DATE CLOSED OUT 1
5 l-RS B Auto-Restart of HPCS 11/20/81 C 11/20/81, 6/11/82 C, SSER #1, 7/82, 7
Rev. 1 5/17/82 P 11/25/81, 9/16/8210 7.3.3.5 R 2/28/83, FSAR App. IA P, SER, 5/82, 7.3.2.1 1
2-RS B Design Adequacy of RCIC 11/20/81 C 11/20/81 P 11/25/817 P, SER, 5/82, 5.4.1, 6.3.1.3 R 4/28/82, FSAR 5.2.2.11 2
3-RSB SPV Surveillance 12/3/81 C 12/3/81 8
P 12/21/81 P, SER, 5/82, 5.2.3 R
3 4-RSB Operator Action (10 min vs. 20 min) 1/25/82 C1/27/8g P 4/1/82 P SER, 5/82, 6.3.3 R
(assumes implementa-tion of II.K.3.18) 3 5-RS B Control of Post-LOCA Leakage 1/25/82 C 1/27/82 P 4/1/829 P, SER, 5/82, 6.3.1.3 R
1 6-RS B Liquid Flow Through SRV 11/20/81 C 11/20/81 P 11/25/817 P, SER, 5/82, 5.4.2 R 4/28/82, FSAR App. IA (See letter from T Novak to LRG-II 1
P,$k},}B99 status 9.
7-RS B Preclude Vortex Formation 11/20/81 C 11/20/81 P 11/25/817 378,2 R
Appendix C, A-43 1
5 8-RSB Long-Term Operability of ADS 11/20/81 C 11/20/81 6/11/82 Rev. 1 5/17/82 P 11/25/817, 9/16/8210 P, SSER #2, 1/83, R
6.3.1.3 e
Page 2 of 9 STATUS OF LRG-If ISSUES PLANT-SPECIFIC ISSUE SUBMITTAL ENDORSEMENT DOCUMENTED NUMBER TITLE DATE DATE CLOSED OUT 5
9-RSB Deep Draft Pump Operability 5/17/82 C 6/11/82 Issue still open P 9/16/8210 R
1 10-RSB Flow Control Valve Closure 11/20/81 C 11/20/8j8 7 P, SER, 5/82, 6.3.3 R
1 ll-RSB Shaft Seizure Event 11/20/81 C 1/2 /
R 12-RSB Proper Classification of Transients 11/20/81 C
/ /
R 2/28/82, FSAR Q.440.51 3
13-RSB Removal of High Drywell Pressure Interlock 1/25/82 C1/27/8g P 4/1/82 P, SER, 5/82, 6.3.1.3 R 2/28/83, FSAR Q.440.36 2
1-CPB Clad Ballooning and Rupture 12/3/81 C 12/3/81 8
P 12/21/81 P, SER, 5/82, 4.2.3.3 R
3 6
2-CPB Seismic and LOCA Loads on Fuel 1/25/82 C 1/27/82, 9/23/8 Issue still open Rev. 1 9/3/82 P 4/1/829, 9/16/82 0 R
4 5
3-CPB Channel Box Deflection 3/12/82 C 3/30/82, 6/11/82 Rev. 1 S/17/82 P 4/1/829, 9/16/8210 P, SSER #2, 1/83, 4.2.3.1 R
N
Pig's 3 of 9 STATUS OF LRG-II ISSUES PLANT-SPECIFIC ISSUE SUBMITTAL ENDO!!SEMENT DOCUMENTED NUI1BER TITLE DATE DATE CLOSED OUT 1
4 4-CPB High Burn-Up Fission Gas Release 11/20/81 C 11/20/81, 3/30/82 Rev. 1 3/12/82 P 11/25/817, 4/1/829 P SER, 5/82, 4.2.3.3 R
1 5-CPB Cladding Water-Side Corrosion 11/20/81 C 11/20/81 7 P 11/25/81 P SER, 5/82, 4.2.3.1 R
5 6-CPB Inadequate Core Cooling Instrumentation 5/17/82 C 6/11/82 No longer being addressai P 9/16/8210 by LRG-11.
Issue being R
handled through BWR 1
A w s Group.
7-CPB Rod Withdrawal Transient Analysis 11/20/81 C 11/20/81 P 11/25/817 P, SER, 5/82, 15.4.2 R
1 8-CPB Mislocated or Misoriented Fuel Bundles 11/20/81 C 11/20/81 7 P 11/25/81 P, SER, 5/82, 15.4.3 R
1 9-CPB Void Coefficient Calculation 11/20/81 C 11/20/81 P 11/25/817 P, SER, 5/82, 4.3.2.2 R
1 10-CPB Bounding Rod Worth Analysis 11/20/81 C 11/20/81 P 11/25/817 P, SER, 5/82, 15.4.4 R
4 11-CPB Core Thermal-Hydraulic Stability 3/12/82 C 3/30/82 P 4/1/829 P, SER, 5/82, 4.4.4 R
Paga 4 of 9 STATUS OF LRG-II ISSUES PLANT-SPECIFIC ISSUE SUBMITTAL ENDORSEMENT DOCUMENTED NUMBER TITLE DATE DATE CLOSED OUT C3/30/8g' l-CSB Containment Dynamic Loads 3/12/82 P 4/1/82 P. SER, 5/82, 6.2.1.8 R
5 2-CSB' Hydrogen Control Capability 5/17/82 C 6/11/82 No longer being addressal P 9/16/8210 by LRG-II.
Issue being R
handled through Hydrogen 3
control owners Croup.
1-AEB MSIV Leakage Rate 1/25/83 C 1/27/82 P 4/1/829 P, SER, 5/82, 15.3.1 R
2 l-ASB Scram Discharge Volume Modifications 12/3/81 C 12/3/81 P 12/21/818 P, SER, S/82, 4.6 R 4/28/82, FSAR Q.410.17 5
2-ASB Safe Shutdown for Fires 5/17/82 C 6/11/82 NG P 9/16/8210 R
4 3-ASB Line Break in Main Steam Tunnel 3/12/82 C3/30/8g P 4/1/82 P, SER, 5/82, 3.6.1 R
1 4-ASB RCIC Pump Room Cooling System 11/20/81 C 11/20/81 P 11/25/817 P, SER, 5/84 9.4.5.3 R
6 5-ASB Control Rod Drive System Vessel Inventory 9/3/82 C 9/23/82 Make-up Test P 9/16/8210 P, SSER #3, 4/83, 4.6 R
l 1
i
Prg2 5 of 9 STATUS OF LRG-II ISSUES PLANT-SPECIFIC ISSUE SUBMITTAL ENDORSE!!ENT DOCUMENTED NUI13ER TITLE DATE DATE CLOSED OUT 1
1-RAB Exposure from SRV Actuation 11/20/81 C 11/20/81 P 11/25/817 P, SER. 5/82, 12.4 R
1 2-RAB Routine Exposures Inside Containment 11/20/81 C 11/20/81 P 11/25/817 P, SER, 5/82, 12.2 1 R
1 3-RAB Radioactivity During Dryer / Separator Transfers 11/20/81 C 11/20/81 P 11/25/817 P, SER. 5/82, 12.2.1 R
1 4-RAB Shielding of Transfe'r Tube & Canal During 11/20/81 C 11/20/81 NG Refueling P 11/25/817 R
1 5
l-ICSB Vessel Level Sensing Line Failure 11/20/81 C 11/20/81, 6/11/82 Rev. 1 5/17/82 P 11/25/817, 9/16/8210 P, SSER #2, 1/83, R
7.7.2.3 0
2-ICSB Redundancy of Iligh/ Low Pressure Interlocks 5/17/82 C 6/11/82 P 9/16/8210 P, SER, 5/82, 7.6.2.1 R
2 3-ICSB Failure of Lowest Low-Low Set Valve 12/3/81 C 12/3/81 8
P 12/21/81 P, SER, S/82, 7.6.2.2 R
4 4-ICSB IE Bulletin 80-06, ESF Reset 3/12/82 C 3/30/82 C SSER 32, 5/83 7.3.3.7 P 4/1/829 P, SER, 5/82**, 7.3.2.5 R
2 e
Page 6 of 9 STATUS OF LRG-II ISSUES PLANT-SPECIFIC ISSUE SUBMITTAL ENDOI SE!!ENT DOCUMENTED NUI1BER TITLE DATE DATE CLOSED OUT 3
5-ICSB Control Systems Failure 1-25-82 C 1/27/82 NG P 4/1/829 R
3 6-ICSB Procedures Following Bus Failure 1/25/82 C1/27/8g NG P 4/1/82 R
3 7-ICSB liarsh Environment for Electrical Equipment 1/25/82 C1/27/8g gg P 4/1/82 R
4 l-PSB Diesel Generator Reliability 3/12/82 C3/30/8g P 4/1/82 P SER, 5/82***, 9.6.3 R
e 1-GIB Unresolved Safety Issues 1/25/82 C Not Endorsed P. SER, 5/82, Appendix C P 4/1/829 R
1 3
l-HFS Special Low Power Testing Program 11/20/81 C 11/20/81,
P. SSER #1, Chap. 14 7, 1/27/824/1/829 (Issue currently being Rev. 1 1/25/82 P 11/25/81 R 8/31/82, FSAR 14.2.12.3.28 reevaluated by NRC) 5 2-IIFS Reactivity Emergency Procedures 5/17/82 C 6/11/82, Not Endorsqd Generic SER for BWR Rev. 1 9/3/82 P Not Endorsed, 9/16/824v Owners' Group EPGs R
Rev. 2 February 4, 1983 from D. G. Eisenhut 1
6 3-liFS Vessel Level Reference Common 11/20/81 C 11/20/31, 9123/82 C SSER #2, 5/83,7.5.35 Rev. 1 9/3/82 P Not Endorsed R
STATUS OF LRG-II ISSUES PLANT-SPECIFIC ISSUE SUBMITTAL ENDORSE!!ENT DOCDtENTED NUI!BER TITLE DATE DATE CLOSED OUT 4
1-CHEB Reactor Coolant Sampling 3/12/82 C 3/30/82 C SSER #2, 5/83, 9.3.5 2 P 4/1/829 R
C 3/ g f' 2-CHEB Suppression Pool Sampling 3/12/82 C SSER #2, S/83, 9.3.5.2 R
5 6
3-CIIEB Post-Accident Sampling Core Damage 5/17/82 C 6/11/82, 8/23/82 C SSER f f,*T/83, 9.3.5.2 Estimates Rev. 1 9/3/82 P Not Endorsed, 9/16/8210 R
4 1-MEB SRSS for Mechanical" Equipment 3/12/82 C3/30/8g P 4/1/82 P, SER, 5/82, 3.9.3.1 R 2/28/83, FSAR Q.210.69 3
2-!EB RPV Internals Vibration 1/25/82 C 1/27/8 P SER, 5/82, 3.9.2.3 P 4/1/82 (See letter from T. Novi R
(NRC) to LRG-II on issue status, 8/17/82) 3 3-!EB OBE Stress Cycles 1/25/82 C1/27/8g P 4/1/82 P, SER, 5/82, 3.9.1 R 2/28/83 FSAR Q.210.63 6
4-MEB Kuo Sheng Incore Instrument Tube Break 9/3/82 C 9/23/82 Issue still open P 9/16/8210 R
3 l-MTEB Flued Head Inspectability 1/25/82 C 1/27/8 P4/1/82g P SER, 5/82, 3.6.2 R N/A O
E" STATUS OF LRC-II ISSUES PLANT-SPECIFIC ISSUE SUBMITTAL ENDORS E!!ENT DOCUMENTED NUl!BER TITLE DATE DATE CLOSED OUT 4
1-SEB Combination of Loads 3/12/82 C 3/30/82 See letter from T. Novak P 4/1/829 (NRC) to LRG-II on R 8/3I/82, FSAR Q.220.53 issue status, 8/17/82.
C3/30/8g' 2-SEB Fluid-Structure Interaction 3/12/82 See letter from T. Novak P 4/1/82 (NRC) to LRG-II on R
issue status, 8/17/82.
C-Clinton P-Perry R-River Bend
- Resolved through first cycle
- Resolved for GE scope of design; unrescived for balance-of-plant design aspects
- Resolved; requires design modifications and procedural changes prior to first refueline'on an interLm basis Resolved procedural upgrade required by fuel load NG-Determined to be non-generic 9
O
Page 9 of 9 Endorsement Letters - Clinton Power Station Unit 1 1.
Letter from G.
E. Wuller to James R. Miller dated November 20, 1981, U-0339.
2.
Letter from G. E. Wuller to James R. Miller dated December 3, 1981, U-0343.
3.
Letter from G. E. Wuller to James R. Miller dated January 27, 1982, U-0410.
4.
Letter from G. E. Wuller to James R. Miller dated March 30, 1982, U-0454.
5.
Letter from G. E. Wuller to Harold Bernard dated June 11, 1982, U-0501.
6.
Letter from G. E. Wuller to Cecil 0. Thomas dated September 23, 1982, U-0551.
Endorsement Letters - Perry Nuclear Power Plant, Units 1 and 2 7.
Letter from Dalwyn R. Davidson to James R. Miller dated November 25, 1981.
8.
Letter from Dalwyn R. Davidson to James R. Miller dated December 21, 1981.
9.
Letter from Dalwyn R. Davidson to James R. Miller dated April 1, 1982.
- 10. Letter from Dalwyn R. Davidson to James R. Miller dated September 16, 1982.
Endorsement Letters - River Bend Station Units 1 and 2 Note:
Gulf States Utilities is endorsing LRG-II positions via reference in the River Bend FSAR rather than by letters.
i
--e
.----.,--e e
n
..-n,e.-,e.
, -- -