ML19276E491

Forwards Proposed Amend to License DPR-65,changing Tech Specs to Incorporate Reactor Coolant Pump Speed Sensing Sys. W/Affidavit & Oversized Drawing

ML19276E491
Person / Time
Site:	Millstone
Issue date:	03/02/1979
From:	Counsil W NORTHEAST UTILITIES
To:	Reid R Office of Nuclear Reactor Regulation
References
TAC-46174, NUDOCS 7903140278
Download: ML19276E491 (17)

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March 2, 1979 Docket No. 50-336 Director of Nuclear Reactor Regulation Attn Mr. R. Reid, Chief Operating Reactors Branch #4 U. S. Nuclear Regulatory Commission Washington, D. C.

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References:

(1)

W. G. Counsil letter to R. Reid, dated November 8,1978.

(2)

W. G. Counsil letter to R. Reid, dated February 12, 1979.

(3)

W. G. Counsil letter to R. Reid, dated January 17, 1979.

Gentlemen:

Millstone Nuclear Power Station, Unit No. 2 Proposed Revisions te Technical Specifications In Reference (1), Northeast Nuclear Energy Company (NNECO) identified its intent to incorporate a reactor coolant pump speed sensing system in order to provide protection exclusively for the four pump loss of flow incident. This system is an addition to the Millstone Unit No. 2 Reactor Protection System (RPS) and would replace the current steam generator differential pressure (Ap) system only for the four pump loss of flow event.

The Ap system will remain in service with its setpoint determined by all other events for which flow measurement is required.

This proposal was further discussed during our meeting on November 21, 1978, and at that time, NNECO indicated that a formal license amendment request would be docketed.

Pursuant to 10CFR50.90, Northeast Nuclear Energy Company hereby proposes to amend its operating license, DPR-65, by incorporating the revisions identified in Attachment 1 into the Millstone Unit No. 2 Technical Specifications.

The new system is identified as a separate Reactor Protective System Functional Unit, Underspeed - Reactor Coolant Pumps. This addition has been made to all applicable tables within the Technical Specifications as reflected in Attach-ment 1.

The surveillance requirements proposed are comparable to those in existence for other functional units of the RPS.

It is noted that on Page 2-5, the proposed trip setpoint has been omitted. Although the four pump loss of flow has been completed and submitted via Reference (2), the trip setpoint has not as yet been finalized. As soon as the final value has been determined, the information will be forwarded to the NRC Staff as a supplement to this submit tal.

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, Qualification details of the RCP speed sensing system are provided as Attach-ment 2.

The entire installation is in conformance with standards comparable to, or in excess of, those standards applied to all other RPS functional units, including the single failure criterion. Attachment 2 also lists all the pertinent equipment and installation documents utilized for the speed sensing system.

The changes provided as Attachment 1 have been reviewed pursuant to the require-ments of 10CFR50.59 and have been found to not constitute an unreviewed safety question.

The qualificar. ion and design of the RCP speed sensing system is comparable to

t. hat of other RPS functional units.

The Millstone Unit No. 2 Nuclear Review Board has reviewed and approved the above proposed change, and concurred in the above determination.

NNECO has reviewed this proposal pursuant to the requirements of 10CFR170, and has determined that no additional fee is required. This submittal is an integral part of the power uprating ef fort and is covered by the payment enclosed in Reference (3).

Very truly yours, NORTIIEAST NUCLEAR ENERGY COMPANY a

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W. 'G. Counsil Vice President Attachment

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Then personally appeared before me W. G. Counsil, who being duly sworn, did state that he is Vice President of Northcast Nuclear Energy Company, a Licensee herein, that he is itherized to execute and file the foregoing information in the name and oti behalf of the Licensees herein and that the statements contained in said information are true and correct to the best of his knowledge and belief.f. hay Notary Public My Commissica Expires March 31, 1031

DOCKET NO. 50-336 ATTACIDIENT 1 MILLSTONE UNIT NO. 2 REACTOR COOLANT PUMP SPEED SENSING SYSTDI PROPOSED REVISIONS TO TECHNICAL SPECIFICATIONS MARCH, 1979

. -[ April 19, 1978 TABLE 2.2-1 (Continued) P r-REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT LIMITS FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES E

10. Loss of Turbine -- Hydraulic

-> S00 psig ~> 500 psig U Fluid Pressure - Low (3) m 11. Underspeed - Reactor Coolant Pumps (1) rpm 1 rpm. 4 TABLE NOTATION (1) Trip may be bypassed below 5% of RATED THERMAL POWER; bypass shall be automatically removed when THERMAL POWER is > 5% of RATED THERMAL POWER. (2) Trip may be manually bypassed below 600 psia; bypass shall be automatically removed at or above 600 psia. (3) Trip may be bypassed below 15% of RATED THERMAL POWER; bypass shall be automatically removed when THERMAL POWER is > 15% of RATED THERMAL POWER. (5) Each of four channels actuate on the auctioneered output of two transmitters, one frm esch steam generator.

[ 2.2 LIMITING SAFETY SYSTEM SETTINGS BASES Underspeed - Reactor Coolant Pumps The Underspeed - Reactor Coolant Pumps trip provides core protection to prevent DNB in the event of a sudden significant decrease in reactor coolant pump speed (and flow) on all four reactor coolant pumps. The trip setpoint ensures that a reactor trip will be generated, considering instrument errors and response times, in sufficient time to allow the DNBR to be maintained above 1.19 following a 4 pump loss of flow event. MILLSTONE - LNIT 2 B 2-8

April 19, 1978 3j TABLE 3.3-1 (Continued) Sh REACTOR PROTECTIVE INSTRUMENTATION o* r MINIMUM si TOTAL NO. CHANNELS CHANNELS APPLICABLE

q FUNCTIONAL UNIT OF CilANNELS TO TRIP OPERABLE MODES ACTION

11. Wide Range Logarithmic Neutron Flux Monitor - Shutdown 4

0 2 3, 4, 5 4

12. Deleted 13.

Underspeed - Reactor 4 2(a) 3 1,2(e) 2 Coolant Pumps N. u , 44

April 19, 1978 TABLE 3.3-2 2 g REACTOR PROTECTIVE INSTRUMENTATION RESPONSE TIMES n oM FUNCTIONAL UNIT RESPONSE TIME 1. Manual Reactor Trip i 2.0 seconds M 2. Power level - High 1 0.40 seconds *# and 1 8.0 seconds ## 3. Peactor Coolant Flow - Low 1 0.65 seconds 4. Pressurizer Pressure - High 1 0.90 seconds S. Containment Pressure - High Not Applicable 6. Steam Generator Pressure - Low i 0.90 seconds 7. Steam Generator Water level - Low 1 0.90 seconds 8. Local Power Density - High 1 0.40 seconds *# and 1 8.0 seconds ## g 9. Themal Margin / Low Pressure 1 0.90 seconds *# and 1 8.0 seconds ##

10. Loss of Turbine--Ilydraulic wb Fluid Pressure - Low Not Applicable 11.

Underspeed - Reactor < 0.45 seconds Coolant Pumps

• Neutron detectors are exempt from response time testing. Response time of the neutron flux Signal portion of the channel shall be measured from detector output or input of first electronic component in channel.

1. Response time does not include, contribution of RTDs.
   1. RTD response time only. This value is equivalent to the time interval required for the RTO's output I

~ to achieve 63.2% of its total change when subjected to a chanac in RTD temperature.

April 19, 1978 TABLE 4.3-1(Continuedl l REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE REQUIREMENTS A e E CliANNEL H0 DES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT R ECK_ CALI_BRATION TEST REQUIRED

11. Wide Range Logarithmic Neutron S

N.A. S/U(1) 3, 4, 5 and

• Flux Monitor

12. Deleted.

13. Reactor Protection System logic N.A.

N.A. M and S/U(1) 1, 2

14. Reactor Trip Breakers N.A.

N.A. M 1, 2 and

• y 15.

Underspeed - Reactor Coolant S R M 1, 2 Pumps cn

DOCKET NO, 50-336 ATTAC101ENT 2 MILLSTONE UNIT No. 2 REACTOR COOLAITT PUMP SPEED SENSING SYSTDI SYSTDI QUALIFICATION AND DESIGN DOCUMENTATION LISTING MARCH, 1979

Introduction At the November 21, 1978 meeting in your offices, several areas of concern were raised by the Staff regarding qualification of the RCP Speed Sensing System. This Attachment addresses those concerns, and lists the documents which specify and qualify each major component of the system. A block diagram of a typical installation is also provided. Cable Separation All power and signal cabling design is in accordance with Millstone Unit No. 2 FSAR Sections 8. 7.1.1 through 8.7.3.2. Cable current carrying capacities and tray / conduit fill are well within acceptable limits in all cases. Existing cable separation criteria are fully observed for the four independent signal channels and for the four 120 VAC vital power source feeds (Zl, Z2, Z3, Z4) supplying the speed sensing system equipment. Seismicity Qualifying documents for seismicity of all equipment are identified in Table 1. Independent analysis of the seismic test data indicates that all test accelera-tion plots envelop the calculated accelerations at the control room and contain-ment mounting locations for the DBE. All components are qualified for seismic conditions in accordance with IEEE 344-1975. Environmental Qualification System components are qualified for environmental conditions in accordance with IEEE 323-1971. As stated in Ref erence (1), operations of the speed sensing system is not required during or subsequent to any Design Basis Event which significantly alters the containment environment (LOCA, Main Steam Line Break, Feedwater Line Break); therefore, it is not required that in-containment equip-ment be qualified for the adverse environments associated with these events. Detailed environmental information, including design temperature, pressure, humidity, and radiation levels is provided in the documents listed in Table 1. IEEE 323-1971 Acceptability All equipment has been procurred, tested, and qualified to IEEE 323-1971. Comparing this certification to that required by IEEE 323-1974, the only major applicable difference is in the area of equipment aging. An independent analysis of the certification provided with the equipment will be undertaken by NNECO to verify that in both the normal and any expected short term ubnormal environment, degradation due to aging during the 40-year lifetime of the equip-ment will not occur to an unacceptable extent. The equipment specifications (referenced in Table 1) require design bases for 40-year lifetime. Surveillance Requirements The Millstone Unit No. 2 Technical Specifications for RPS functional units currently require a " Channel Check" every shif t, a " Channel Functional Test"

~ . monthly, and " Channel Calibration" every refueling. This surveillance will be performed in accordance with the definitions of these tests provided in the Technical Specifications. Design Documentation SKRJB021579-1 Block Diagram Shts. 1-4 25203-26032 Piping and Instrument Diagram Reactor Coolant Pump 25203-26014 Piping and Instrument Diagram Reactor Coolant System 25203-28005R Reactor Coolant System Panel CO2R, C03R Rear View 25203-39045 Wiring Diagram Shts. 53, 54 Panel C03R, C04R 25203-39045 Reactor Coolant System Shts. 67, 70 Wiring Diagram, Rear View SKRJB021579-2 Conduit Schedule SKRJB021579-3 Cable Schedule Shts. 1, 2 20613* Outline - 95 Ohm, 300 HA Probe 21710* Outline - 95 Ohm Extension Cable 2170l* Outline - Pulse Transmitter 18556* Outline - Signal Processor Ass'y. 18732* Bin Ass'y. 21930* Outline - Power Supply 21950* Outline - Regulator 21940* Outline - Pulse Shaper 18938* Schematic Diagram - Power Supply 18939* Schematic Diagram - Regulator Assembly 18940* Schematic Diagram - Pulse Shaper Assembly 25203-39069 Schematic Diagram - Reactor Shts. 9-16, 18-25 Protective System 25203-39070 Bistable Trip Unit Schematic Sh. 1 25203-39070 Bistable Trip Unit Parts List Sh. 3 25203-29200 Bistable Trip Unit Module Ass'y. Sh. 1 25203-31081 Connection Diagram - RPS Trip Unit 25203-31083 RPS Terminal Block Wiring Diagram 25203-31084 RPS Terminal 25203-31085 RPS Terminal 25203-31096 RPS Terminal 25203-32045 Reactor Trip Switchgear Shts. 1-8 25203-39107 Reactor Coolant Flow - Channels P-111,121, and 101 Sht. 11 Interconnection Diagram 25203-39107 RCP Zero Speed and 90% Speed Sht. 23 Interconnection Diagram 25203-29148 General Electric RCP Motor Drawing Sht. 1 Table of Contents / Ambient Conditions

• Indicates - Bently Nevada Drawing No.

. 25203-29148 General Electric Connection Diagram Sht. 6 Speed Switch and Zero Speed Switch D-18767-416-141 RCP Zero and 90% Speed Interconnection Diagram (C.E. Dwg.) 25203-30022 Vital A-C Panels - One line Sht s. 10-13 25203-30024 Vital A-C - One Line 25203-27017 Vital A-C Equipment Room 25203-34029 East Penetration Roum 25203-34030 West Penetration Room 25203-34042 Containment (Elev. 14 ' 6") 25203-34043 Containment (Elev. 38'6") 25203-27027 Control Room Arrangement 791E693, 791E694 General Electric Motor Outlines - Model No. 295 X 290 S/N 8384970, 8384971, 8384972, 8384973, (G. E. Dwg s. ) Additional Drawings Signal Processing Chassis Power Supply, Component Arrangement Regulator, Component Arrangement Pulse Shaper, Component Arrangement Power Supply, Wire List Regulator, Wire List Pulse Transmitter, Wire List Bin Assembly, Wire List Power Supply, Parts List Regulator, Parts List Pulse Transmitter, Parts List Bin Assembly, Parts List Connector Assembly

. System Connection Diagram Tagging and Color Code Instruction Manual Frequency-to-Voltage Converter Recommended Spare Parts List Equipment Outline Drawings Assembly and Components Arrangement Elementary and Schematic Drawings Terminal Wiring List or Drawings Seismic Documentation Instruction Manual Insert

TABLE 1 SPEED SENSING SYSTEM COMPONENTS Component Sp_eci fica tion /Quali fica tion Proximity Probe A, C Coaxial Cable A Pulse Transmitter A, D Signal Processor A, D F/V Converter B Bistable E 3/C #16 Signal Cable F 3/C d12 Power Cable G LEGEND A Combustion Engineering Specification No. 00000-ICE-6003, Revision No. 02, Dated 12/18/75 - Engineering Specification for a Reactor Coolant Pump Shaft Speed Sensing System B Combustion Engineering Specification No. 00000-ICE-3035, Revision No. 00, Dated 11/9/78 - Engineering Specification for a Frequency To Voltage (F/V) Circuit Assembly C Combustion Engineering (CENPD-182) Seismic Test Documentation, Data Sheet No. 205 (2 pages), Revision No. 01, Dated 3/77 - Proximity Probe and Connector D Combustion Engineering (CENPD-182) Seismic Test Documentation, Data Sheet No. 2j (2 pages), Revision No. 01, Dated 3/77 - Pulse Transmitter and Signal Processor E Bechtel Specification No. 7604-M-806 Bistable Trip Unit F Northeast Utilities Service Company Specification No. SP-GEE-14, Revision No. 1, Dated 7/1/78; Kerite Test Report C-7684, Item Nos. l A,1B,1C, ID - 3C #16 Shielded Cable G Northeast Utilities Service Company Q.A., Stock Code No. 13600017 - 3/C *12 Cable

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l C04R 27JOf'egoc. PN ER S UPPLY 76 0 RE GU L ATOR goi 6SH LD RC 0 5 A CY - 13 4 -1 A B\\ STABLEDWG 310Sl 5ULSE SHAPER p R E GUL ATOR [AW2-Tfl) SY - 135 -1 A PULSE SHAPER REG U L ATOR SY -136-I A PULSE SHARER j REGULATOR SY-13 7-I A DULSE SHAPER

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