ML20010E915
| ML20010E915 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 09/01/1981 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Bauer E PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| References | |
| NUDOCS 8109090101 | |
| Download: ML20010E915 (11) | |
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NSIC ACRS-10 cket F1 ORB #4 Rdg Gray File NE VUK DEisenhut L PDR JStolz TERA MFairtile Dockets Nos. 50-277 RIngram b I @f and 50-273 IE-P 6.
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..#2 j b,O\\g ftr. Edward G. Dauer, Jr.
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Philadelphia Electric Company
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2301 thrket Street Philadelphia, Pennsylvania 19101
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Dear !!r. Bauer:
By letter dated July 7,1980, we requested that you propose Technical Specification changes for Peach Botton Station, Units 2 and 3 to pro-vide surveillance requirenents for scram discharge volume (SDV) vent and drain valves and LC0/ surveillance requirercnts for RPS and control rod block SDV limit switches.
Our consultant, Franklin Research Center (FRC) has reviewed your sub-mittal in response to this letter and has identified the need for addi-tional infomation. We have evaluated the FRC document and agree that this infomation is needed in order to complete our review.
Accordingly, please provide the additional infomation requested in the enclosure within forty-five (45) days of your receipt of this letter.
If you or your staff have any questions on this matter, please contact your project mnager.
Sincerely, a0 RIG 12AL SIG'ED #I J0tEl F. SW
John F. Stolz, Chief Operating Reactors Branch #4 Division of Licensing
Enclosure:
Request-for Additionsl Infomation cc w/ enclosure:
See next page 8109090101 810901 PDR ADOCK 05000277 P
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OFFICIAL RECORD COPY usaro. im.-33 co nac ronu ais oo.so> sacu eno
Philadelphia Electric Company cc w/ enclosure (s):
Eugene J. Bradley Philadelphia Electric Company Regional Radiation Representative Assistant General Counsel EPA Region III 2301 Market Street Curtis Building (Sixth Floor)
Philadelphia, Pennsylvania 19101 6th and Walnut Streets Philadelphia, Pennsylvania 19106 Troy B. Conner, Jr.
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1747 Pennsylvania Avenue, N.W.
' M. J. Cooney, Superintendent Washington, D. C.
20006 Generation Division - Nuclear Philadelphia Electric Company Raymond L. Hovis, Esq.
2301 Market Street 35 South Duke Street Philadelphia, Pennsylvania 19101 York, Pennsylvania 17401 Government Publications Section
,. Warren K. Rich, Esq.
State Library of Pennsylvania Assistant Atterney General Educatio'n Building Department of Natural Resources Commonwealth and Walnut Streets Annapolis, Maryland 21401 Harrisburg, Pennsylvania 17126 Philadelphia Electric Company ATTN:
Mr. W. T. Ullrich Peach Bottom Atomic Power Station Mr. Rr A. Heiss, Coordinator Del,ta, Pennsylvania 17314 Pennsylvania State Clearinghouse Governor's Office of State Planning Albert R. Steel, Chairman ahd Development Board of Supervisors P. O. Box 1323 Peach Bottt.n Township Harrisburg, Pennsylvania 17120 R. D. =1 Delta', Pennsylvania 17314 Curt Cowgill U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Peach Botton Atomic Power Station P. O. Box 399 Delta, Pennsylvenia 17314 6
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REQUEST FOR ADDITIONAL INFORMATION BWR SCRAM DISCHARGE VOLUME LONG-TERM MODIFICATIONS PHILADELPHIA ELECTRIC COMPANY
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PEACH BOTTOM NUCLEAR POWER STATION UNITS 2 AND 3 NRC DOCKET NO. 50-277, 50-278 NRC TAC NO.
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BACKGRCJ4D This Request for additional Information (RFI) is the result of an evaluation of information contained in a letter dated October 14, l'>80 from Philadelphia Electric Company, 2301 Market Street, PO Box 8699, Philadelphia, PA 19101 to the Nuclear Regulatory Commission (NRC) in response to NRC's request for Technical Specifications changes regarding Peach Bottom Nuclear Power Station Units 2 and 3 surveillance requirements for scram discharge volume (SDV) vent and drain valves, and limiting conditions for operation (LCO)/ surveillance requirements for reactor protection system lRFS) and control rod block SDV limit switches. The evaluation was made in accordance with criteria contained in the Model Technical Specifications proposed by NRC staff and incorporated in'to the General Electric Star.dard Technical Specifications.
2 The evaluation revealed four items of concern to which unsatisfactory responses were obtained, one item of concern refers to surveillance requirements for 3DV drain and vent valves; two items of concern refer to LCO/ surveillance requirements for reactor protection system SDV limit switches; and one item.of concern refers to LCO/ surveillance requirements for control rod block SDV limit switches.
Additional information related to these items of concern is needed before a final evaluation of the proposed Technical Specification changes for Peach Bottom Nuclear Power Station Units 2 and 3 can be made.
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REQUESTED C'.fANGES IN TECHNICAL SPECIFICATIONS The changes in Technical Specifications involve surveillance requirements of the main components and instrumentation of the scram discharge volume.
They cover three areas cf concern, as described below.
I.
Surveillance Recuirements for SDV Drain and vent Valves The surveillance requirements of the Model Technical Specifications for SDV drain and vent valves are:
"4.1.3.1.1 - The scram discharge volume drain and vent valves shall be demonstrated OPERABLE at least once per 31 days by:
a.
Verifying each valve to be open*, and b.
Cycling each valve at least one complete cycle of full travel.
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"*These valves may be closed intermittently for testing under administrative controls."
Philadelphia Electric Company's response to the above surveillance requirements for SDV drain and vent valves is given in the subsequent paragraph:
" Surveillance Requirements for SDV Vent and Drain Valves "b.
The scram discharge volume drain and vent valves shall be verified open at least once per month. These valves may be closed intermittently for testing.
"c.
At least once every 3 months verify that the scram discharge volume drain and vent valves closed within 15 seconds af ter receipt of a closure signal, and reopen upon reset of the closure signal."
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ITEM 1 CONCERN Philadelphia Electric Company's response in paragraph c should read "At least once per 31 days.
" in place of "At least once every 3 months..." to comply with paragraph 4.1.3.1.lb of the Model Technical Specifications.
REQUEST 1.
Provide a revised page 100 of the Technical Specifications for Peach Bottom Nuclear Power Station Units 2 and 3 where the requested change for surveillance requirements of the drain and vent valves is incorporated, or 2.
Provide realistic technical bases why the requested change is not applicable to Peach Bottom Nuclear Power Station Units 2 and 3.
II.
LCO/ Surveillance Recuirements for Reactor Protection System Scram Discharce Volume Limit Switches The required changes in the Technical Specifications with reference to LCO/ surveillance requirements for reactor prettetion system scram discharge volume limit switches are given in the NRC staff's Model Technical Specifications as reproduced below.
"3.3.1 - As a minimum, the reactor protection system instrumentation channels shown in Table 3.3.1-1 shall be OPERABLE with the REACTOR PROTECTION SYSTEM RESPONSE TIME as shown in Table 3.3.1-2.
"4.3.1.1 - Each reactor protection system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST, and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.1.1-1."
The required information from the tables referred to in the above paragraphs follows.
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o Table 3.3.1-1.
Reactor Protection System Instrumentation Applicable Minimum Operable Functional Operational Channels Per Trip Unit Conditions System (a)
Action 8.
Scram Discharge Volume Water Level-High 1,2,5 (h) 2
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4 NOTATION:
(a) A channel may be placed in an inoperable status up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for required surveillance without placing the trip system in the tripped condition provided at least one OPERABLE channel in the same trip system is monitoring that parameter.
(h) With any control rod withdrawn. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.
Action 4: In OPERATIONAL CONDITION 1 or 2, be in at least HOT SHUTDOWN within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
In OPERATIONAL CONDITION 5, suspend all operations involving CORE ALTERATIONS
- and fully insert all insertable control rods within one hour.
- Except movement of IRM, SRM or special movable detectors, or replacement of LPRM strings provided SRM instrumentation is OPERABLE per Specification 3.9.2.
Table 3.3.1-2.
Reactor Protection System Response Times Functional Response Time Unit (Seconds) 8.
Scram Discharge Volume Water Level-High NA Table 4.3.1.1-1.
Reactor Protection System Instrumentation Surveillance Requirements Channel Operational Functional Channel Functional Channel Conditions in Which Unit Check Test Calibration Surveillance Required
- 8. Scram Discharge Volume Water Level-High NA M
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ITEM 2 CONCERN Referring
- .o paragraph 3.3.1 and Table 3.3.1-1 c! th<s Model Technical Specifications given above, the Technical Specifications for Peach Bottom Nuclear Power Station Units 2 and 3 should contain a similar paragraph.and table or an equivalent paragraph stating that, as a minimum, the reactor protection system scram discharge volume water level-high instrumentation shall consist of two CPERABLE channels containing two limit switches per trip system, for a total of four OPERABLE channels containing four limit switches per two trip systems, making 1-cut-of-2 taken twice logic.
DEQUEST Provide a reference to that section of the Technical Specifications for Peach Bottom Nuclear Power Station Units 2 and 3 which indicates that the reactor protection system SDV water level-high consists of 2 OPERABLE channels containing two limit switches per trip system, for a total of 4 OPERABLE channels containing 4 limit switches per two trip systems, making 1-out-of-2 taken twice logic.
ITEM 3 CCNCERN Referring to paragraph 4.3.1.1 and Table 4.3.1.1-1 of the Model Technical Specificat' ons, the Technical Specifications for Peach Bottom Nuclear Power i
Station should contain a similar paragraph and table or an equivalent paragraph stating that each reactor protection sy' stem scram discharge volume water level-high instrumentation channel containing a limit switch shall be demonstrated CPERAboE by the performance of the CHANNEL FUNCTIONAL TEST once per month and CHANNEL CALIBRATION operations each refuelling outage for the OPERATIONAL CONDITIONS 1, 2, and 5.
Page 42, Table 4.1.1 of the Technical Specifications for Peach Bottom Units 2 and 3 provides only 'for the CHANNEL FUNCTIONAL TEST once per month as requested in the Model Technical Specifications. It does not provide for CHANNEL CALIBRATION operations each refuelling outage,
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3 REQUEST
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Provide a reference to the pages of the Technical Specification where CHANNEL CALIBRATION operations each refuelling cutage.are specified, or 2.
Provide technical bases why the CHANNEL CALIBRATION operations each refuelling outage should not be performed.
III.
LCO/Strveillance Requirements for Control Rod Block Scram Discharge Volume Limit Switches The provisions of the Model Technical Specifications in regard to LCO/surveill'ance requirements for control rod bicek scram discharge volume limit. switches are:
"3.3.6.
The control rod withdrawal block instrumentation channels shown in Table 3.3.6-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.6-2.
"4.3.6.
Each of the above required control rod withdrawal block trip systems and instrumentation channels shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.6-1."
The information contained in the tables referred to in the above paragraphs follows.
Table 3.3.6-1.
Control Rod Withdrawal Block Instrumentation Minimum Operable Applicable Channels Per Trip Operational Trip Function Function Conditions Action
- 5. Scram Discharge volume a.
Water Level-High 2
1,2,5**
62 b.
Scram Trip Bypassed 1
1,2,5**
62
- With more than one control rod withdrawn. Not applicable to control rods '
removed per Specification 3.S.10.1 or 3.9.10.2.
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With the number of OPERABLE channels less than required by the minimum OPERABLE channels per trip function requirement, place the inoperable channel in the tripped condition within one hour.
Table 3..~.6-2.
Control Rod Withdrawal Block Instrumentation Setpoints Trip Function Trip Setpoint Allowable Value 5.
Scram Dist,,irge Volume
- a. Water Level-High 125 gallons 125 gallons
- b. Scram Trip Bypassed NA NA Table 4.3.6-1.
Control Rod Withdrawal Block Ins'trumentation Surveillance Requirements Channel Operational' Channel Functional Channel Conditions In Which Trip Function Check Test Calibration Surveillance Recuired 5.
Water Level-High NA Q
R 1,2,5**
b.
Scram Trip Bypassed NA M
NA 1,2,5**
- As in Table 3.3.6-1.
ITEM 4 CONCERN Refe'rring to paragraph 3.3.6 and Table 3.3.6-1 of the Model Technical Specifications, the Technical Specifications for Peach Nuclear Power Station Units 2 and 3 should contain a similar paragraph and table or an equivalent paragraph concerning the control rod withdrawal block scram discharge volume water level-high instrumentation and scret trip bypassed instrumentation.
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o Philadelphia Electric Company's response indicates that the Peach Bottom Nuclear Power Station Units 2 and 3 have only one channel containing one limit switch for the control rod withdrawal block SDV water level-high and presumably SDV scram trip bypassed instrue.entation is not available.
REQUE$t Provide technical bases for not providing scram trip bypassed ins
- tation and for not incorporating LCO/ Surveillance requirements into the Bottom Technical Specifications.
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