ML20215K044
| ML20215K044 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 04/28/1987 |
| From: | Gallagher J PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Butler W Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.E.4.2, TASK-TM NUDOCS 8705110047 | |
| Download: ML20215K044 (5) | |
Text
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PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET P.Op. BOX 8699 PHILADELPHIA PA.19101 12151 841 5001 April 28, 1987 sosa,w w.
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Docket Nos. 50-277 50-278 Mr. W. A. Butler, Director Directorate I-2 Division of Reactor Projects I/II U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D.C.
20555
SUBJECT:
Peach Bottom Atomic Power Station NUREG-0737, Item II.E.4.2(7)
High Radiation Isolation of Vent and Purge Lines
REFERENCES:
(1) Letter dated May 7, 1986 from R. M.
Bernero, NRC, to J. M.
- Fulton, BNR Owners Group (2) Letter dated January 25, 1984 from S.
L.
Daltroff, PECo, to J.
F.
Stolz, NRC
Dear Mr. Butler:
This letter responds to the Reference (1) letter as requested by former NRC Peach Bottom Project Manager, G. Gears, and updates the implementation schedule for a modification required to comply with a TMI " Lesson Learned" requirement (NUREG-0737, Item II.E.4.2/7).
The Reference (1) letter establishes the NRC's criteria for exempting lines of two inches in diameter or smaller from this NUREG-0737 requirement for high radiation isolation signals based on the NRC's review of analyses provided by the BWR Owners Group (BWROG) in submittals dated June 14, 1982 and June 27, 1981, and in NSEO-78-0882.
The Reference (1) letter stated that:
BWR lines of 2 inches in diameter or smaller need not be provided with a radiation isolation signal, provided that a licensee demonstrates on his docket that the BWROG evaluation is applicable to his plant.
This demonstration should include an assessment of the ability of the operators to assess and isolate leakages that would not cause other isolation signals (e.g.,
verification of the BWROG generic assertion of a maximum of 30 minutes)."
bg 8705110047 870428 DR ADOCK 05000277 dg
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Mr. W. A.
Butler April 28, 1987 Page 2
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Philadelphia Electric Company has determined that the BWROG evaluation is applicable to Peach Bottom Atomic Power-Station Units 2 and 3.
There are sufficient indications and alarms in the control room for the operators to assess leakages, and the small purge and vent valves can be remotely closed by hand switches in the control room.
Therefore, the control room operators could assess and isolate leakages that would not cause other isolation signals within 30 minutes.
Attached is a list of indications and alarms which are available to the operators.
The emergency procedures implemented in accordance with NUREG-0737 and the associated training program identify the conditions and operator actions required to assure containment isolation.
In accordance with the Reference (1) letter, we consider high radiation isolation signals for lines 2 inches in diameter or smaller to be unnecessary.
The Reference (2) letter, dated January 25, 1984, proposed an implementation schedule of.1985 for Unit 3 and 1986 for Unit 2 based on an earlier understanding that the high radiation trips would apply only to the large lines.
As a result of the subsequent discussions regarding the applicability of this NUREG-0737 requirement and the efforts of the BWROG to obtain NRC approval to exclude the small lines, implementation of the modification was deferred.
Based on the clarification of the regulatory requirement provided by the Reference (1) letter, dated May 7, 1986, the implementation schedule for high radiation trips is prior to startup after the 1987 outages on both Unit 2 and Unit 3.
If you have any questions or require additional information, please do not hesitate to contact us.
Very truly yours, b
LJ,3<~f 8 Attachment cc:
W. T.
Russell, Administrator, NRC, Region I T.
P. Johnson, Resident Site Inspector R.
E. Martin, NRC Project Manager
'\\--
Attachmant Docket Nos. 50-277 50-278 Page 1 of 3 INDICATIONS AND' ALARMS IN CONTROL ROOM FOR ASSESSING RADIATION LEAKAGE DRYWELL PRESSURE Instrument (1)
Alarm
^
PR-4805 No (PR-5805)
PR-8102A,B No (PR-9102A,B)
I PI-2508 Yes (H/L)
(PI-3508) and PR-2508 (PR-3508)
DRYWELL TEMPERATURE Instrument (1)
Alarm TR-4805 No (TR-5805)
TI-2501-19 to 27 No (TI-3501-19 to-27)
TI-2501-35 to 39 No (TI-3501-35 to 39)
TI-2501-63 to 66 No (TI-3501-63 to 66)
CONTAINMENT HIGH RANGE AREA RADIATION Instrument (1)
Alarm RR-8103A,B*
Yes (H)
(RR-9103A,B)*
(1)
Instrument numbers in parenthesis apply to Unit 3, others apply to Unit 2.
j
- Four channels are indicated on two dual-pen indicator recorders, s
Attachm5nt Docket Nos. 50-277 50-278 Page 2 of 3 DRYWELL ATMOSPHERE PARTICULATE, IODINE AND NOBLE GAS RADIATION Instrument Alarm One Alarm on CO3 Panel Yes (H-H/H/L) actuated by local RIS-4130, 4131, 4132 (Unit 2) and RIS-5130, 5131, 5132 (Unit 3)
REFUELING FLOOR VENTILATION EXHAUST RADIATION Instrument (1)
Alarm RIS-17-458A,B,C,D Yes (H-H,H,L)*
and RR-17-456 on Panel 20C10 (RIS-17-458A,B,C,D and RR-17-456 on Panel 30C10)
REACTOR BUILDING VENTILATION EXHAUST RADIATION Instrument (1)
Alarm RIS-17-452A,B,C,D Yes (H-H,H,L)*
and RR-17-455 on Panel 20C10 (RIS-17-452,A,B,C,D and RR-17-455 on Panel 30C10)'
-MAIN STACK EXHAUST RADIATION Instrument Alarm RIS-17-50A,B Yes (H-H,H,L)**
and RR-17-51 (common to both units)
- Isolates on H-H
- Containment Isolation on H-H to be installed under Hi Rad. Isolation Modification (Mod. No. 664).
-1 Attcchmsnt l-Docket Nos. 50-277 50-278 Page'3 of 3 VENT STACK EXHAUST RADIATION Instrument (1)
Alarm RIS-2979A&B Yes (H-H,H/L)
(RIS-3979A&B) and RR-2979 (RR-3979)
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