ML20151D064
| ML20151D064 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 04/06/1988 |
| From: | Shemanski P Office of Nuclear Reactor Regulation |
| To: | Butterfield L COMMONWEALTH EDISON CO. |
| References | |
| TAC-59107, TAC-59108, NUDOCS 8804130377 | |
| Download: ML20151D064 (8) | |
Text
April 6, 1988 Docket Nos. 50-373 and.50-374 DISTRIBUTION PM OGC-Rockville NRC~ & Cocal' PDRs EJordan PDIII-2 Rdg.
JPartlow Mr. L. D. Butterfield, Jr.
DCrutchfield ACRS (10)
Nuclear Licensing Manager GHolahan PDIII-2 Plant Comonwealth Edison Company LLuther File Post Office Box 767 PShemanski Chicago, Illinois 60690
Dear Mr. Butterfield:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION ON THE ATWS REVIEW FOR LASALLE COUNTY STATION, UNITS 1 AND 2 (TAC N0s. 59107 AND 59108)
Comonwealth Edison Company provided information by letters dated April 6, and October 23, 1987 concerning the implementation of the ATWS Rule (10 CFR 50.62) for the LaSalle County Station, Units 1 and 2.
However, the information provided is not sufficient to determine compliance with the Comission's regulations.
We have prepared the enclosed request for additional information (RAI) on the alternate rod injection (ARI) and the recirculation pump trip (RPT) systems.
We request that this information be provided by April 20, 1988 in order to meet our scheduled Safety Evaluation date for this issue.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under r
P.L.96-511.
I Sincerely, Paul Shemanski, Project Manager Project Directorate III-2 Division of Reactor Projects - III, IV, Y and Special Projects
Enclosure:
As stated sc:
See next page p..c.
PDIII-2:PM PDIII-2:fL PD I
- PD f
PShemanski:bj LLuther-d-D r
4 / 6/88 4/4/88 t//4/88 8804130377 080406 PDR ADOCK 05000373 P
Y LaSalle County Nuclear 'ower Station Mr. L. D. Butterfield, Jr.
Units 1 and 2 Commonwealth Edison Company cc:
John W. McCaffrey Philip P. Steptoe, Esq.
Chief. Public Utilities Division Sidley and Austin SOIC One First National Plaza 100 West Randolph Street, Suite 12 Chicago, Illinois 60603 Chicago, Illinois 60601 Assistant Attorney General 100 West Randolph Street Chicago, Illinois 60601
)
Resident inspector /LaSalle, NPS U.S. Nuclear Regulatory Commission i
Rural Route No. 1 P.O. Box 224 l
Marseilles. Illinois 61341 i
J Chairman LaSalle County Board of Supervisors LaSalle County Courthouse Ottawa, Illinois 61350 Attorney General l
500 South 2nd Street Springfield, Illinois 62701 J
Chairman Illinois Commerce Comission Leland Building 527 East Capitol Avenue Springfield, Illinois 62706 Mr. Michael C. Parker, Chief Division of Engineering Illinois Department of Nuclear Safety 1035 Outer Park Drive, 5th Floor Springfield, Illinois 62704 Regional Administrator, Region III j
U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 i
\\'
ENCLOSURE 1
REQUEST FOR ADDITIONAL INFORMATION ON ATWS REVIEW RELATED TO ALTERNATE ROD INJECTION (ARI) AND RECIRCULATION PUMP TRIP (RPT) SYSTEMS LASALLE STATION UNITS 1 & 2 (1)
In your 10/23/87 letter Attachment 1 Item 1 it was indicated that the ARI is initiated 15 seconds after a recirculation pump trip on High Reactor Vessel Pressure (1135 psig). Please clarify that 15 seconds is not the time delay circuit in the ARI system design.
It is the time to process the signal (such as energize solenoid valve and vent the air at the header). The ARI initiation should start at the same time as RPT.
(2)
It is not clear whether or not that the ARI system and the RPT system use the same sensors and logics. Please provide the electrical functional diagrams for the ARI and the RPT systems from sensors to the final actuated devices.
(3)
In your 4/6/87 submittal, it was indicated that the ARI channel ccaponents employ linear analog transmitters and trip units while the reactor protection system (RPS) employs differential pressure and pressure switches. However, in your revised submittal dated 10/23/87, it stated that separate sensors are used for the RPS. Please identify the specific instrurt.ent rrodels installed at the LaSalle plant for the ARI system and the RPS (such as Rosemount transmitter Model 1153, trip unit Model 510DU,
.. etc.)
i (4) Your ATWS-RPT design is very similar to the original BWR/4 RPT design as described in the BUROG topical report NEDE-31096-P.
The BWR/4 RPT design war found not acceptable during the staff's review on BWROG topical report NEDE-31096-P. The staff required these utilities to submit their r
~_.
1 2-proposed RPT system upgrade plan or to demonstrate that their present design can perform its function in a reliable manner equivalent to the two approved designs (the Monticello design and the modified Hatch design).
The statement in the SER (NUREG-0519 section 15.2.1, dated March 1981) was an acceptable basis for interim operation of LaSalle pending the outcome of the commission rulemaking on anticipated transients without scram.
Therefore, the staff has not concluded that the ATWS-RPT design at LaSalle was in conformance with the ATWS Rule. Please provide the information required by sections 7.0 and 7.1 of the Safety Evaluation of topical report NEDE-31096-P, to justify a design which is different from the reference designs.
I 4
l l
f a
d 1
t April 6, 1988 Docket Nos. 50-373 and 50-374 DISTRIBUTION Docket Fue OGC-Rockville NRC & Local PDRs EJordan PDIII-2 Rdg.
JPartlow Mr. L. D. Butterfield, Jr.
DCrutchfield ACRS(10)
Nuclear Licensing Manager GHolahan PDIII-2 Plant Comonwealth Edison Company LLuther File Post Office Box 767 PShemanski Chicago, Illinois 60600
Dear Mr. Butterfield:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION ON THE ATWS REVIEW FOR LASALLE COUNTY STATION, UNITS 1 AND 2 (TAC N0s 59107 AND 59108)
Comonwealth Edison Company provided information by letters dated April 6, and October 23, 1987 concerning the implementation of the ATWS Rule (10 CFR 50.62) for the LaSalle County Station, Units 1 and 2 However, the information provided is not sufficient to determine compliance with the Comission's regulations.
We have prepared the enclosed requcst for additional information (RAI) on the alternate rod injection (ARI) and the recirculation pump trip (RPT) systems.
We request that this information be provided by April 20, 1988 in order to meet our scheduled Safety Evaluation date for this issue.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.
i Sincerely.
Paul Shemanski, Project Manager Project Directorate III-2 Division of Reactor Projects - III.
IV, Y and Special Projects 1
Enclosure:
As stated cc:
See next page P. s.
PDIII-2:PM PDIII-2:L PD f
- PD l
0Shemanski:bj LLuther - -
O ar 4 / 6/88 4/G/88 g/4/88 u
~
i 4
LaSalle County Nuclear Power Station Mr. L. D. Butterfield, Jr.
Units I and 2 Comonwealth Edison Company cc:
John W. McCaffrey Philip P. Steptoe Esq.
Chief, Public Utilities Division Sidley and Austin SOIC One First National Plaza 100 West Randolph Street, Suite 12 Chicago, Illinois 60603 Chicago, Illinois 60601 Assistant Attorney General 100 West Randolph Street Chicago, Illinois 60601 Resident Inspector /LaSalle, NPS U.S. Nuclear Regulatory Comission Rural Route No. 1 P.O. Box 224 Marseilles, Illinois 61341 Chainnan LaSalle County Board of Supervisors LaSalle County Courthouse Ottawa, Illinois 61350 Attorney General S00 South 2nd Street Springfield, Illinois 62701 Chainnan Illinois Comerce Comission Leland Building 527 East Capitol Avenue Springfield, Illinois 62706 Mr. Michael C. Parker, Chief Division of Engineering i
Illinois Department of Nuclear Safety 1035 Outer Park Drive, 5th i4oor Springfield, Illinois 6P704 Regional Administrator, Region III U.S. Nuclear Regulatory Comission 799 Roosevelt Road i
Glen Ellyn, Illinois 60137
ENCLOSURE 1
REQUEST FOR ADDITIONAL INFORMATION ON ATWS REVIEW RELATED TO ALTERNATE ROD INJECTION (ARI) AhD RECIRCULATION PUMP TRIP (RPT) SYSTEMS LASALLE STATION UNITS 1 & 2 (1)
In your 10/23/87 letter Attachment 1 Item 1 it was indicated that the ARI is initiated 15 seconds after a recirculation pump trip on High Reactor Yessel Pressure (1135 psig). Please clarify that 15 seconds is not the time delay circuit in the ARI system design.
It is the time to process the signal (such as energize solenoid valve and vent the air at the header). The ARI initiation should start at the same time as RPT.
(2)
It is not clear whether or not that the ARI system and the RPT system use the sarre sensors and logics. Please provide the electrical functional diagrams for the ARI and the RPT systems from sensors to the final actuated devices.
(3)
In your 4/6/87 submittai, it was indicated that the ARI channel components employ linear analog transmitters and trip units while the reactor protection system (RPS) employs differential pressure and pressure switches. However, in your revised submittal dated 10/23/87, it stated that separate sensors are used for tne RPS. Please identify the specific instrument models installed at the LaSalle plant for the ARI system and the RPS (such as Rosemount transmitter Model 1153, trip unit Model 51000,
.. etc.)
(41 Your ATWS-RPT design is very similar to the original BWR/4 RPT design as described in the BUROG topical report NEDE-31096-P. The BWR/4 RPT design was found not acceptable during the staff's review on BWROG topical report NEDE-31096-P. The staff required these utilities to submit their
},
1 4
i 2
l proposed RPT system upgrade plan or to demonstrate that their present design can perfonn its function in a reliable manner equivalent to the two f
approveddesigns(theMonticellodesignandthemodifiedHatchdesign).
The statement in the SER (NVREG-0519 section 15.2.1, dated March 1981) was an acceptable basis for interim operation of LaSalle pending the outcome of the comission rulemaking on anticipated transients withuut scram.
Therefore, the staff has not concluded that the ATWS-RPT desi:n at LaSalle was in confonnance with the ATWS Rule.
Please provide the infonnation required by sections 7.0 and 7.1 of the Safety Evaluation of topical report NEDE-31096-1, to justify a design which is different from the reference designs.
i i
.