ML18038A074

Forwards FSAR Changes Which Address SER Confirmatory Item 25 Re LPCI & LPCS Valve Interlocks.One Oversize P&ID Drawing Also Encl

ML18038A074
Person / Time
Site:	Nine Mile Point
Issue date:	10/30/1985
From:	Mangan C NIAGARA MOHAWK POWER CORP.
To:	Butler W Office of Nuclear Reactor Regulation
Shared Package
ML17054B965	List: ML17054B964 ML18038A074
References
(NMP2L-0523), (NMP2L-523), NUDOCS 8511010304
Download: ML18038A074 (24)

Text

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REGULATORY IN ORMATION DISTRIBUTION SYSTIIF.. (RIDS)

"ACCESSION" NBR;8511010304

. DOC,OATEN'5/10/30 NOTARIZED:" NO DOCKET' FACIL:50'10 Ninel Mile>> Point Nuclear>>'Station<

Unit>> 2'~ Niagar a Moha>>

05000410 AUTH',NAMEf AUTHOR AFFILIATION MANGAN'rO', V >.

Niagora>> Mohawk>> Powe'r Cor p; REC IP ~ NAMEI RECIP IENT'FF ILIA'TION BUTLER'rI>>t~

licensing Branch 2'SUBJECT Forwards>>

FSAR changes which'ddress SER'>>Confii matory Item-25 rei LPCII L LPCS'al ve>> interlocks;One>>

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NIAGARAMOHAWKPOWER CORPORATION/300 ERIE BOULEVARDWEST, SYRACUSE, N.Y. 13202/TELEPHONE (315) 474-1511 October 30, 1985 (NMP2L 0523)

Dr. Walter Butler, Chief Licensing Branch No.

2 U.S. Nuclear Regulatory Commission Washington, OC 20555

Dear Or. Butler:

Re:

Nine Mile Point Unit 2 Docket No. 50-410 Enclosed are changes to the Final Safety Analysis Report which address Safety Evaluation Report Confirmatory Item Number 25, Low Pressure Coolant Injection and Lower Pressure Core Spray valve interlocks.

Also attached are Piping 8 Instrumentation Diagrams of the Low Pressure Coolant Injection and Low Pressure Core Spray which will be incorporated into the Final Safety Analysis Report.

These changes will be included in FSAR Amendment 23.

Very truly yours, C. V. Mangan Senior Vice President BB/rla Enclosure 1015G xc:

R. A. Gramm, NRC Resident Inspector Project File (2) 85i 10i 0304 851030 PDR ADO'5000410-PDR

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Nine Nile Point Unit 2 FSAR After receipt of the initiation 'signals and after a delay provided by timers, each of the two solenoid pilot air valves are energized.

This allows pneumatic pressure from the accumulator to.act on the air cylinder operator.

Each ADS trip system timer can be reset manually to delay system initiation. If reactor vessel water level is restored by the HPCS prior to the end of the time delay, ADS initiation will be prevented.

The ADS trip system A actuates the A solenoid pilot valve on each ADS relief valve.

Similarly, the ADS trip system B ac-tuates the B solenoid pilot valve on each ADS relief valve.

Actuation of either solenoid pilot valve causes the as-sociated ADS valves to open to provide depressurization.

Once initiated, the ADS logic seals in and can be reset by the control room operator only when either drywell pressure or vessel water level returns to normal.

The ADS actuation logic is further discussed in Section 1.10, Task II.K.3.18.

The control switches (one for each trip system solenoid) are located in the main control room for each SRV associated with the ADS.

Each switch controls one of the two solenoid pilot valves.

Testabilit Refer to Section 7.3.2.1.3, Conformance to Regulatory Guide 1.22.

7.3.1.1.1.3 Low Pressure Core Spray Instrumentation and Controls S stem Function The purpose of the LPCS is to provide low-pressure reactor vessels core spray following a LOCA when the vessel has been depressurized and vessel water level has not been restored by the HPCS.

The LPCS is functionally diverse from the LPCI mode of the RHR system.

S stem 0 eration Schematic arrangements of system mechanical equipment are shown on Figure 6.3-4.

LPCS components control logic is shown on Figure 7.3-5.

Instrument specifications and chan-nel requirements are listed in Table 7.3-3.

Operator in-formation displays are shown on Figures 6.3.4 and 7.3.5.

7.3-6

~

I 4

/

Nine Mile Point Unit 2 FSAR The LPCS is initiated automatically by reactor vessel low water level and/or high drywell pressure.

The system is designed to operate automatically for at least 10 min without any action required by the control room operator.

Once initiated, the LPCS logic seals in and can be reset by the control room operator only when the water level and drywell pressure return'o normal.

Refer to Figure 7.3-5 for a schematic representation of the LPCS system initiation logic.

Reactor vessel water level (Trip Level 1) is monitored by two redundant level transmitters.

Drywell pressure is monitored by two redundant pressure transmitters.

The ves-sel level trip unit relay contacts and the drywell pressure trip unit relay contacts are connected in a one-out-of-two-twice logic arrangement so that no single instrument failure can prevent initiation of the LPCS.

The LPCS components respond to an automatic initiation sig-nal simultaneously (or sequentially as noted) as follows:

1.

The Division I diesel generator is signaled to start.

2.

The normally closed test return line to the sup-pression pool valve MO F012 (MOVlOS) is signaled closed.

3

~

When power (offsite or onsite) is available at the IPCS pump motor bus, the LPCS pump is signaled to start.

If offsite power is available, the LPCS pump starts after a 10-sec delay.

If offsite power is not available and

-the Division I diesel generator is providing power, the 'LPCS pump starts after a 6-sec delay.

4.

A differential pressure transmitter senses the pressure differential between the low pressure side of LPCS injection valve MO F005 (HOV104) and reactor vessel pressure.

When the pressure differential is low enough to protect the LPCS from overpressure and power is available to the pump motor

bus, the injection valve is signaled to open.

The LPCS pump discharge flow is monitored by a differential pressure transmitter.

When the pump is running and dis-charge flow is low enough to cause pump overheating, the minimum flow return line valve MO F011 (MOV107) is opened.

The valve is automatically closed if flow is normal.

7. 3-7

E

~

J

Nine Mile Point Unit 2 FSAR The LPCS.

pump suction from the suppression pool valve MO F001 (MOV112) is normally open, and the control switch is keylocked in the open position and thus requires no automatic open signal for system initiation.

7. 3-7a

~

~

~

~

Nine Mile Point Unit 2 FSAR

. The LPCS pump and injection valve have manual override con-trols that permit the operator to manually control the sys-tem subsequent to automatic initiation.

\\

Testabilit Refer to Section 7.3.2.1.3, Conformance to Regulatory Guide 1.22.

7.3.1.1.1.4 RHR Low Pressure Coolant Injection Mode-Instrumentation and Controls S stem Function The LPCI is an operating mode of the RHR system.

The pur-pose of the LPCI mode is to, provide low pressure reactor vessel coolant makeup following a LOCA when the vessel has been depressurized and vessel water level is not maintained by the HPCS.

S stem 0 eration Schematic arrangements of system mechanical equipment are shown on Figure 5.4-13.

LPCI component control logic is shown on Figure 7.3-6.

Instrument specifications are listed in Table 7.3-4 and Chapter 16.

Elementary diagrams are identified in Section 1.7.

Operator information displays are shown on Figures 5.4-13 and 7.3-6.

The LPCI system is initiated automatically by xeactor vessel low water level and/or by high drywell pressure.

The system is designed to operate automatically for at least 10 min without any action required by the control room operator.

Once initiated the LPCI logic seals in and can be reset, by the control room operator when initial conditions return to normal.

Refer to Figures 5.4-13 and 7.3-6 for a schematic representation of the LPCI A and the LPCI B/C initiation logic, respectively.

Reactor vessel water level (Trip Level 1) is monitored by two redundant differential pressure transmitters.

To provide diversity, drywell pressure is monitored by two redundant pressure transmitters.

To initiate the Division II LPCI (Loops B and C), the vessel level transmitter contacts and the two drywell "pressure transmitter contacts are connected in a one-out-of-two twice

'arrangement so that no single instrument failure can prevent initiation of LPCI.

7.3-8

a

~

~

A

~

~

I Nine Mile Point Unit 2 FSAR

- The Division I,LPCI (Loop A) receives its initiation signal from the LPCS logic.

The LPCI system components respond to an automatic initiation signal simultaneously (or sequen-tially as noted) as follows (the Loop A components are con-trolled from the Division I logic; the Loop B and C com-ponents are controlled from the Division II logic):

The Division I

and II diesel generators are sig-naled, to start.

2.

If offsite power is available at the pump motor

buses, the LPCI pumps A and B start after a

5 sec time delay; LPCI pump C and the LPCS pump start af-ter a

10 sec time delay.

If offsite power is not available and diesel generators are providing power to the pump motor buses, sequential loading of the diesel generators is required.

This is accom-plished by starting LPCI pumps A

and B

after a

1 sec time delay; LPCI pump C and the LPCS pump start after a

6 sec time delay.

3.

Differential pressure transmitters monitor the pressure difference between the low pressure side of each LPCI injection valve MO F042A (MOY24A),

F042B (MOY24B),

F042C (MOY24C) and reactor pressure.

When the differential is low enough and power is available at the associated pump motor bus, the injection valve is signaled to open.

The following normally closed valves are signaled closed to ensure proper system lineup:

RHR heat exchanger discharge to.RCIC valves MO F026A (MOV32A), F026B (MOV32B) and AO F065A (LV17A), F065B (LV17B).

b.

d.

e.

RHR heat exchanger flush to suppression pool valves MO F011A (MOV37A), F011B (MOV37B).

RHR heat exchanger steam pressure reducing valves AO FOSlA (PV21A),

F051B (PV21B).

RHR heat exchagner steam inlet isolation valves MO F052A (MOV22A), F052B (MOV22B) and F087A (MOV23A), F087B (MOV23B).

Test return line to the suppression pool valves MO F024A (FV38A),

F024B (FV38B) and F021 (FV38C).

7. 3-9

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Nine Mile Point Unit 2 FSAR

'f.

. Containment spray to suppression pool valves MO FO27A (MOV33A), FO27B (MOV33B).

g, h.

Steam condensing mode drain line valves

F106A, B (SOV70A, B) and F107A, B (SOV71A, B).

RHR sample valves

F060A, B (SOV36A, B) and

F075A, B (SOV35A, B).

7.3-9a

~

~

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Nine Mile Point Unit 2 FSAR nals whenever the primary system pressure exceeds subsystem design pressure will close MOVs F053 (one-out-of-two logic),

isolating the line.

Valve position indication for these valves is provided in the control room.

In the RHR head spray line, testable check valves E51-F065 and E51-F066 are in series with MOV E12-F023.

Two low pres-sure permissive signals (two-out-of-two logic) are required for MOV F023 to open.

Removal of either signal will close the valve (one-out-of-two logic).

Valve position indication for all three valves is provided in the control room.

Because LPCI injection valves E12-F042A, B,

and C are part of the emergency'core coolant system (ECCS),

only

'a LOCA signal and low differential pressure permissive signal are provided to open valves F042 as is required.

Testable check valves E12-F041A, B,

and C are downstream of valves F042.

LPCS injection valve E21-F005 is part of the ECCS and includes only a LOCA signal and a low differential pressure permissive signal to open as is required.

Testable check valve E21-F006 is downstream of valve F005.

In the RHR steam condensing mode lines, valves E12-F052A and B are in series with valves E12-F087A and B

and E12-F051A and B.

A LOCA signal will prevent all three valves in each line from opening and will close all three if they were open.

Valves F087 have a high pressure interlock that will not allow valves F087 to open and will also close valves F087 on high steam line pressure.

Valves F051 are electrop-neumatic converter-controlled air-operated throttle valves.

These valves will begin to close at a set heat exchanger shell pressure.

The valves will be completely closed before the line's design pressure is-.exceeded:

Operating power to valves F051 are supplied from an essential power source.

IEEE 279 is applied at the system level to the protection system containing high pressure/low pressure interlocks.

7.6. 1.3 Leak Detection Syst: em Instrumentation and Controls The safety-related portions of the LDS are as follows:

1.

Main steam 1'ine leak detection (7.3. 1, 7.2. 1.2.2) 2.

RCIC system leak detection.

3.

RHR 'system leak detection (7.3.1).

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