ML16340B550
| ML16340B550 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 03/19/1981 |
| From: | Check P Office of Nuclear Reactor Regulation |
| To: | Tedesco R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8104020298 | |
| Download: ML16340B550 (14) | |
Text
a Docket Nos:
50-275 and 50-323 MAR 19 1981 g g/pp 4f~
MEMORANDUM FOR:
Rober t L, Tedesco, Assistant Director for Lic FROM:
Paul S. Check, Assistant Director for Plant Systems, DSI
SUBJECT:
D MLO CANYON FULL POWER RE(UIREHENTS << THI ISSUES ln the memorandum, H. Denton, to D. Ross, et. al., FebtAary 27. 1981, a
list of issues to be resolved for Diablo Canyon full p'ower operation identified Reactor Systems Branch as the cognizant branch for a number of Items.
IIhe following is our statement of the status of those items:
THI ISSUES OFFICE/
SURNAME) 0ATE f>
l.
I.G.l Low Power Test Results - RSB findings are reported in the memorandum P.
C ec, to R. Te esco, e ruary 17, 1981.
Item found acceptable.
PIE has committed to provide test results prior to operation at power levels exceeding
~I55 of full power.
2.
II.K.I ESP Posttlons - Revlma previously complete; IIIem aicceptable, see Diablo Canyon SER, Supplement 10, August 1980.
3.
IIFF.2 Instrumentation to Detect Inade uate Core Coolin t - CPB has lead respons ity or t s
tern; RSB is avai a
e to ass st 'as needed.
4.
II.K.2 Item 13 Thermal-Mechanical Re ort - RSB review complete; item accepta e;
SER enc os 5.
II.K.2 Item 17 Voidin in RCS - RSB review complete; item acceptable.
SER enc ose II.K.2. Item 19 Benchmark Anal",si
<<>Se uential AFtl Flow - RSB review complete; tern acceptable; SER enc ose 7.
II.K.3 (tern 1
Automatic PORV Isolation - In SER input (P. Check to R.
e esco February 20, 1981 we identified that the applicant would provide a )<aport >arltten by the Ifestlnghouse Ouners Group to address NUREG-0737 item II.K.3.2 on a schedulesmeeting the intent of the NUREG-0737 schedule, which >@ found acceptable.
If indicated by the staff review of this report and ongoing staff generic studies, we will require that an automatic PORV isolatiop system be implemented at Diablo Canyon tIn a schedule consistent with t;)'e intent of NUREG-0737, Item II.K.3.1.
lie find the applicant's comaittment acceptable for full pal'er operation.
CONTACT:
Frank Orr, NRR gpss 1 8 1981 dd~
NRC FORM 3181)0/80) NRCM 0240 OFF I CIA L R EGO R D COPY 9 USGFO: 198~29.824
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4 Robert L. Tedesco MAR l 9 198t h
8.
II.K.3, Item'2 Re ort on PORV Failures - RSB review complete;,,item accep-ta e;
see RSB S R, P.
Ghee to R. T
- esco, February 20, 1981.
9.
II.K.3 Item 3 Re ortin of Safet and Relief Va90e Failures - RSBVreview complete; item acceptable; see RSB SER, P.
Check R. Tedesco, February 20, 1951.
10.
II.K.3 Item 5, Automatic Tri of HC
~t RSB review complete; item accepta e;
SER enc ose 11.
II.K.3 Item 10, dao osed Antici ator Tri Modifications - Review prev ous y comp ete; tern accepta e; see D a o Canyon SER, Supplement 10, August 1980.
12.
II.K.3 Item 11 Justif Use of Certain PORV - Review previously complete; item accepta le; gee D ab o Canyon
- SER, Supp ement 10, August 1980.
13.
II.K.3 Item 17 ECCS Outa es - RSB review complete, item acceptable; SER enclosed; DST will perform follow-up if necessary.
14 II.K.3 Item 25 Power on Pum Seals - RSB review complete.
item acceptable; SER enc os 15.
II.K.3 Item 30 SB LOCA Anal aks - RSB revtem complete, Item acceptable:
sea R,
Fe ruary 20, 98.
The enclosed SERs and the SERs previously forwarded resolve RSB TMI issues for full power operation.
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II.K.3 Item 31 Plant S ecific Anal ses - RSB review complete; item acceptable; SER enc osed.
Enclosure:
As Stated cc:
D. Ross T. Speis F. Miraglia G. Mazetis B. Sheron V. gancIera Buck1ey B. Hardin R. Audette J.
Guttmann F. Orr C. Liang G. Alber thai Paul S. Check, Assistant Director for Plant Systems Division of Systems Integration Distribution:
Docket File ~
RSB R/F PSCheck OFFICE/
SURNAME/
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DSI:RS J:()rl:lcm O3( J8'Si DS B
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B ei 03/ 18/81 03/
/81
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NRC FORM 318110/80) NRCM 0240 OFFICIAL RECORD COPY 29 824
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UNITED STATES NUCLEAR REGULATORY COiYif'IISSlON WASHINGTON, D. C. 20555 tip I ~
1<~~1 Docket Nos:
50-275 and 50-323
'EMORANDUM FOR:
Robert L. Tedesco, Assistant Director for Licensing, DOL FROM:
Paul S.
Check, Assistant Director for Plant Systems, DSI
SUBJECT:
DIABLO CANYON FULL POWER RE(UIREMENTS - THI ISSUES In the memorandum, H. Denton, to D. Ross, et. al., February 27,
- 1981, a
list of issues to be resolved for Diablo Canyon full power operation identified Reactor Systems Branch as the cognizant branch for a number of items.
The following is our statement of the status of those items:
TMI ISSUES l.
I.G.1, Low Power Test Results RSB findings ar e reported in the memorandum P.
Check, to R. Tedesco, February 17, 1981.
Item found acceptable.
PG&E has committed to provide test results prior to operation at power levels exceeding 5% of full power.
2.
II.K.l ESF Positions - Review previously complete; item acceptable, see Diablo Canyon
- SER, Supplement 10, August 1980.
3.
II.F.2 Instrumentation to Detect Inade uate Core Coolino - CPB has lead responsibility for this item; RSB is available to assist as needed.
4.
II.K.2, Item 13, Thermal-Mechanical Re ort - RSB review complete; item acceptable; SER enclosed.
5.
II.K.2 Item 17, Voidin in RCS - RSB review complete; item acceptable, SER enclosed.
6.
II.K.2, Item 19 Benchmark Anal. si Se uential AFM Flow -
RSB review complete; item acceptable; SER enclosed.
7.
II.K.3, Item 1, Automatic PORV Isolation - In SER input (P.
Check to R. Tedesco, February 20, 1981 we identified that the applicant would provide a report written by the Westinghouse Owners Group to address NUREG-0737 item II.K.3.2 on a schedule meeting the intent of the NUREG-0737 schedule, which we found acceptable.
If indicated by the staff review of this report and ongoing staff generic studies, we will requir e that an automatic PORV isolation system be implemented at Diablo Canyon on a schedule consistent with the intent of NUREG-0737, Item II.K.3.1.
!le find the applicant's coIInIittment acceptable for full power operation.
CONTACT:
Frank Or r, NRR X 27591
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Robert L. Tedesco I ~ II ev
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8.
II.K.3, Item 2, Re or t on PORV Failures -
RSB review complete; item accep-table; see RSB SER, P.
Check to R. Tedesco, February 20, 1981.
9.
10.
12.
13.
14.
II.K.3 Item 3, Re ortin of Sa et and Relief Valve Failures - RSB review complete; item acceptable; see RSB SER, P.
Check to R. Tedesco, February 20, 1981.
II.K.3, Item 5, Automatic Tri of RCPs - RSB review complete; item acceptable; SER enclosed.
II.K.3, Item 10, Pro osed Antici ator Tri Hodifications - Review previously complete; item acceptable; see Diablo Canyon
- SER, Supplement 10, August 1980.
II.K.3, Item 11, Justif Use of Certain PORV - Review previously complete; i tem acceptable; see Diablo Canyon SER, Supplement 10, August 1980.
II.K.3 Item 17 ECCS Outa es - RSB review complete, item acceptable; SER enclosed; DST will perform follow-up if necessary.
II.K.3, Item 25, Power on Pum Seals -
RSB review complete, item acceptable; SER enclosed.
15.
16.
II.K.3 Item 30, SB LOCA Anal ses -
RSB review complete, item acceptable; see SER, February 20, 1981.
II.K.3 Item Sl Plant S ecific Anal ses -
RSB review complete; item acceptable; SER enc osed.
The enclosed SERs and the SERs previously forwarded resolve RSB THI issues for full power operation.
gC.J'
. j(!
Paul S.
Check, Assistant Director for Plant Systems Division of Systems Integration
Enclosure:
As Stated CC:
D. Ross T. Speis F. Hiraglia G. Hazetis B. Sheron V. Panciera B; Buckley B. Hardin R. Audette J., Guttmann F. Orr C. Liang G. Alberthal
V
ENCLOSURE II.K.2, Item 13, Thermal-h1echanical Re ort The Westinghouse Owners Group, of which PG&E is a member.
wi 11 address the NRC requirements of detailed analysis of the thermal-mechanical conditions in the reactor vessel during recovery from small breaks with an extended loss of all feedwater.
This program is scheduled to be completed and documented to the NRC by January 1, 1982 and will consist of analysis for generic Westinghouse PWR plant groupings.
Following the completion of this generic
- program, PG&E has committed to supply a plant specific analysis based on the generic analysis, if required.
This schedule is consistent with the requirements of NUREG-0737, and we find the PG&E committment acceptable.
II.K.2, Item 17, Voidin in RCS The Westinghouse Owners Group, of which PG&E is a member, is addressing the potential for void formation in the reactor coolant system (RCS) during natural circulation cooldown conditions, as described in Westinghouse Letter HS-TMA-2298 (T.
M. Anderson, W, to P.
S.
- Check, NRC).
PG&E believes the results of this effort will address the NRC requirement for analysis to the NRC before January 1, 1982.
This schedule is consistent with the requirements of NUREG-0737, and we find the PG&E committment acceptable.
II.K.2 Item 19 Benchmark Anal sis Se uential AFW Flow The transient analysis
- code, LOFTRAN, and the present small-break evaluations analysis
- code, WFLASH, are both undergoing benchmar king against plant information or experimental test facilities.
These codes are also being compared with each
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The Westinghouse Owners Group, of which PGSE is a member, will provide a report addressing the benchmarking of these codes by January 1, 1982.
This schedule is consistentwith the requirements of NUREG-0737, and we find the PG&E committment acceptable.
II.K.3, Item 5 Automatic Tri of RCPs The applicant has referenced WCAP-9584, an analysis performed by the Westinghouse Owners Group using the Westinghouse small-break evaluation model (WFLASH) to show that ample time is available for the operator to trip reactor coolant pumps following certain small breaks.
In addition, the owners group is supporting a best-estimate study using the NOTRUMP computer code to demonstrate that tripping the reactor coolant pump at the worst trip time after a small-break will lead to acceptable resul;ts.
Using both of these analysis
- methods, (WFLASH and NOTRUMP) the Qestinghoase Owners Group has performed post-test predictions of LOFT experiment L3-6.
The input data and model to be used with WFLASH on LOFT L3-6 was submitted by the owners group to the staff on December 1, 1980.
The LOFT prediction using WFLASH is pr'esently under review.
PGSE has committed to supply justification that these models and analyses apply to Diablo Canyon, within 3 months after NRC approval of the models.
This schedule is consistentiwith the requirements of NUREG-0737, and we find the PGEE c'oranittment acceptable.
r
If indicated by results of the approved
- analyses, we will require Diablo Canyon to implement an automatic trip of the RCPs on a schedule consistent with the intent of NUREG-0737.
II.K.3.17, ECCS Outa es Diablo Canyon has provided a committment to adopt a program to identify future outage dates and lenghts of outages.
This committment has included an identification of the listings to be included in their reports and a
further committment to submit a greater detailed breakdown of the reported data.
This p'roposed listing agrees with the required areas identified in NUREG-0737 and is acceptable for full power operation.
II.K.3, Item -25, Effect of Loss of A-C Power on Pum Seals In a letter (P.
Crane to F. Miraglia, February 13, 1981),
PG and E identified that component cooling water pumps and containment isolation valves in the component cooling system providing cooling water to the RCP thermal barriers have emergency on-site backup power and their operability would not be lost with a loss of A-C power.
We find this capability acceptable to meet the requirement for full power operation.
II.K.3, Item 31, Com liance with CFR 50.46 In a submittal (P.
- Crane, PG and E, to F. Miraglia, NRC, February 26, 1981), the applicant has comnitted to submit a
new analysis (using a
new and approved Westinghouse model in accordance with the NRC schedule) if the conclusions of Item II.K.3.30 indicate that the present small break LOCA analysis for Diablo Canyon is not in conformance with 10 CFR 50.46.
We find this commitment acceptable for full power operation.
L SNR ~ 8 198'f