ML20010E892
| ML20010E892 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 09/01/1981 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Beckham J GEORGIA POWER CO. |
| References | |
| TAC-42218, TAC-42219, NUDOCS 8109090052 | |
| Download: ML20010E892 (13) | |
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SEPTEMBER 0 1 1381 DISTR"BUTION:
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4 fir. J. T. Beckham, Jr.
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Dear Mr. Beckham:
By letter dated July 7,1980, we requested that you propose Technical Specification changes for llatch Nuclear Plant, Units 1 and 2 to provide surveillance requirements for scran discharge volume (SDV) vent and drain valves and LC0/ surveillance requirements for RPS and control rod block SDV limit switches.
Our consultant, Franklin Research Center (FRC), has reviewed your sub-nittal in response to this letter and has identified the need for addi-tional infornation. lie have evaluated the FRC document and agree that this information is needed in order to conplete our review.
Accordingly, please provide the additional information 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 natter, please contact your project manager.
Sincerely.
- 0acaaL siczrar JCC F. STOW John F. Stolz, Chief Operating Reactors Branch #4 Division of Licensing
Enclosure:
Request for Additional Informtinn cc u/ enclosure:
See next page 8109090052 810901 PDR ADOCK 05000321 P
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Hatch'l/2 Georgia Power Company 50-321/366 cc w/ enclosure (s):
G. F. Trowbridge, Esq.
Shaw, Pittman, Potts and Trowbridge 1800 M Street, N.W.
Washington, D. C.
20036 Ruble A. Thomas Vice President P. O. Box 2625 Southern Services, Inc.
Birmingham, Alabama 35202 Ozen Batum Charles H. Badger P. O. Box 2625 Office of Planning and Budget Southern Services, Inc.
Room 610 Birmingham, Alabama 35202 270 Washington Street, S.W.
Atlanta, Georgia 30334 Chairman Appling County Commissioners County Courthouse Baxley, Georgia 31513 Mr. L. T. Gucwa Georgia Power Company Engineering Department P. O. Box 4545 Atlanta, Georgia 30302 Mr. Max Manry Georgia Power Company Edwin I. Hatch Plant i
P. O. Box 442 Baxley, Georgia 31513 Regicnal Radiation Representative EPA Region IV 345 Courtland Street, N.E.
At.lanta, Georgia 30308 Appling County Public Library 301 City Hall Drive Baxley, Georgia 31513 Mr. R. F. Rodgers U.S. Nuclear Reculatory Commission Route 1, P. O. Box 279 Baxley, Georgia 31513
REQUEST FOR ADDITIONAL INFORMATION BWR SCRAM DISCHARGE VOLUME i
LONG-TERM MODIFICATIONS GEORGIA POWER COMPANY HATCH NUCLEAR POWER STATION UNITS 1 AND 2 NRC DOCKET NO. 50-321, 50-366 NRC TAC NO. 42219, 42218 1
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BACKGROUND This Request for Additional Informatio. (RFI) is t'.e result of an evaluation of information contained 11 a letter dated February 26, 1981 from Georgia Power Company to the Nuclear Regulatory Commission (NRC) in tesponse to NRC's request for Technical Specifications changes regarding Hatch Nuclear Power Station Units 1 and 2 surveillance requirements for scram discharge volume (SDV) vent and drain valves, and limiting conditions for operation (LCO)/ surveillance requirements for reactor protection system (RPS) and control rod block SDV limit switches. The evaluation was made in accordance with criteria contained in the Model Technical Specifications proposed by NRC staf f and incorporated into the General Electric Standard Technical Specifications.
The evaluation revealed six items of concern to which unsatia actory responses were obtained. One item of concern refers to surveillance requirements for SDV drain and vent valves; two items of concern ' refer to Iro/ surveillance requirements for reactor protection system SDV limit switches; and three items of concern refer 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 tile proposed Technical Specification changes for Hatch Nuclear Power Station Units 1 and 2 can be made.
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r REQUESTED CHANGES IN TECHNICAL SPECIFICATICNS The changes in Technical Specifications involve surveillance requirements of the main components and instrumentation of the scram discharge volume.
They cover three areas of 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 OPER.TBLE at least once per 31 days by:
a.
Verifying each valve to be open*, and Cycling each valve at least one complete cycle of full travel.
b.
"*These valves may be closed intermittently for testing under administrative controls."
ITEM 1 CONCERN Tile Technical Specifications for Hatch Nuclear Power Station Units 1 and 2 should contain a paragraph specifying the surveillance requirements for SDV drain and vent valves similar to paragraph 4.1.3.1.1 of the Model Technical Specifications. The drain and vent valves can be closed and opened (cycled) under administrative controls during normal reactor operation without causing reactor scram.
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PEQUEST
- 1. Provide a reference to that section of the Technical Soecifications for Hatch Nuclear Power Station Units 1 and 2 where the requested changes for surveillance requirements of the drain and vent valves are incorporated, or A
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- 2. Provide realistic technical bases why the requested changes are not applicable to Hatch Nuclear Power Station Units 1 and 2.
II.
LCO/ Surveillance Requirements for Reactor Protection System' Scram i
Discharge Volume Limit Switches The required changes in the Technical Specifications with reference to IrO/ surveillance requirements for reactor protection 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.
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"4'.3.1.1 - Each reactor protection system instrumentation ch 'nr1 sha11 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 f rom the tables referred to in the above paragraphs follows.
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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
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4 Level-High 1,2,5 (h) 2 NMATION:
(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 HM 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 inser' table 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 l
Functional Channel Functional Channel Conditions in Which Unit Check Test Calib r ation Surveillance Required
- 8. Scram Discharge Volume Water Level-High NA M
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ITEM 2 CONCERN Referring to paragraph 3.3.1 and Table 3.3.1-1 of the Model Technical Specifications given above, the Technical Specifications for Hatch Nuclear Power Station Units 1 and 2 should contain a similat paragraph and table or an equivalent paragraph stating that, as a minimum, the reactor pro'tection system scram discharge volume water level-high instrumentation shall consist of two OPERABLE 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-out-of-2 taken twice icgic.
REQUEST
- 1. Provide a reference to that sectioE~of the Technical Specifications for Hatch Nuclear Power Station Units 1 and 2 which indicates that the reactor protection system SDV water level-high consists of 2 OPERABLE channels containing two limit switches per trip system, for e total of 4 OPERABLE channels containing 4 limit switches per two trip systems, making 1-out-of-2 taken twice logic, or
- 2. If the Technical Specifications for Ha'tch Nucletr Power Station Units 1 and 2 do not contain the above requirements, make the required changes and provide a copy of the proposed changes.
ITEM 3 i
CONCERN j
Referring to paragraph 4.3.1.1 and Table 4.3.1.1-1 of the Model Technical Specifications, the Technical Specifications for Hatch Nuclear Power Station Units 1 and 2 should contain a similar paragraph and table or an equivalent t
1 paragraph stating that each reactor protection system scram discharge volume
. ater level-high instrumentation channel containing a limit switch shall be w
i demonstrated OPERABLE by the performance of the CHANNE! FUNCTIONAL TEST once per month and CHANNEL CALIBRATICN operations each refuellino outage for the l
OPERATIONAL CONDITIONS 1, 2, and 5.
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REQUEST
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- 1. Provide a riference to the pages of the Technical Specifications for Hatch Nuclear Power Station Units 1 ane: 2 where the requested changes for ICO/ surveillance requirements of reactor protection system SDV limit switches are incorporated, or
- 2. If the proposed frequency of the required surveillance for Hatch Nuclear Power Station Units 1 and 2 differs from the frequency requested by the Model Technical Specifications, provide technical bases for it.
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LCO/ Surveillance Recuirements for Control Rod Block Scram Discharge
.III.
Volume Limit Switches The provisions of the Model Technical Specifications
.n regard to LCO/ surveillance requirements for control rod block scram discharge volume limit switches are:
2 The control rod withdrawal block ins,trumentation channels shown "3.3.6.
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,C-1."
The information contained in the tables referred to in the above paragraphs follows.
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Table 3.3.6-1.
Control Rod Withdrawal B1c9k Instrumentation Minimum Operable Applicable Trip Channels Per Trip Operational Function Function Cond itions 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 3.9.10.1 og 3.9.10.2.
Action 62: 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 3.3.6-2.
Control Rod Withdrawal Block Instrumentation Setpoints
, Trio Function Trio Setooint Allowable Value 5.
- a. Water Level-High 118 gallons 118 gallons
- b. Scram Trip 3ypassed NA NA Table 4.3.6-1.
Control Rod Withdrawal Block Instrumentation Surveillance Requirements Channel Operational Trip Channel Functional Channel Conditions In Which Function Check Test Calibration Surveillance Required 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.
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CONCERN J
Referring to paragraph 3.3.6 and Table 3.3.6-1 of the Model Techni cal Specifications, the Technical Specifications for Hatch Nuclear P'ower U stion Units 1 and 2 should contain a similar paragraph ar.d table or an equivalent paragraph concerning the control rod withdrawal block scram discharge volume water level-high instrumentation and scram trip bypassed instrumentation.
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REQUEST
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- 1. Provide a reference to the pages of the Technical Soecifications for H,ttch Nuclear Power Station Units 1 and 2 where the number of "MINIMIM OPERABLE CHANNELS PER TRIP FUNCTION" is specified in regard to CCNTROL RCD WITHDRAWAL BLOCK INSTRUMENTATION SDV for i
a.
water level-high b.
scram trip bypassed, or
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- 2. Provide technical bases for deviations from the staf f position.
ITEM S CONCERN Referring to paragraph 3.3.6 and Table 3.3.6-2 of the Model Technical Specifications, the Technical Specifications for Hatch Nuclear Power Station
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Units 1 and 2 should contain a similar paragraph and table or an equivalent paragraph stating the control rod withdrawal block scram discharge volume water level-high.
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REQUEST i
1.
Provide a reference to the pages of the Technical Specifications for Hatch Nuclear Power Station Units 1 and 2 where the setpoint in regard to the control rod withdrawal block SDV water level-high is specified, or 2.
Propose such a change.
ITEM 6 CONCERN Referring to paragraph 4.3.6 and Table 4.3.6-1 of the Model Technical Specifications, the Technical Specifications for Hatch Nuclear Power Station Units 1 and 2 should contain a similar paragraph and table or an equivalent paragraph stating:
Eac.h centrol rod withdrawal block scram discharge volume water level-high instrumentation channel containing a limit switch shall' be demonstrated OPERABLE by the performance of the CHANML FUNCTIONAL TEST once per 3, months and CHANNEL CALIBRATION operations each refuelling outage; a scram trip bypassed instrumentation channel containing a limit switch shall be demonstrated OPERA 3LE by the performance of the CHANNEL FUNCTIONAL TEST once per month. For the surveillance specified above, the OPER.\\TIONAL CONDITIONS shall be 1,
,5**.
- As in Table 3.3.6-1.
REQUEST
- 1. Provide a reference to the pages of the Technical Specifications for Hatch l
Nuclear Power Station Units 1 and 2 where the requested changes for
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ICO/ surveillance requirements for con' vi rod SDV limit switches are incorporated, or 9
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- 2. If the proposed frequency of the required surveillance for Hatch Nuclear Power Station Units 1 a.nd 2 differs frotn the frequency of surveillance requested by the Model Technical Specifications, provide technical bases for it.
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