Text

Amend 3 to License NPF-86,revising Tech Specs Re Removal of RHR Isolation Valve Autoclosure Interlock
	ML20085A753
Person / Time
Site:	Seabrook
Issue date:	07/12/1991
From:	Wessman R; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20085A758	List: ML20085A753; ML20085A768;
References
	NUDOCS 9107260217
	Download: ML20085A753 (12)
	v • d • e

_ _ _ _ _ _ _ _. _ _ _. _. _

e p2 Rf Ch 0

ON g,%

UNITED STATES If i NUCLEAR REGULATORY COMMISSION

% IEj/

'f WASWNGioN. D C. 20M4 o

PUBLIC SERVICE'COMPAt1Y 0_F t1EW HAMPSHIRL ET AL*

DOCKET NO. 50-443 SEABROOK STATION, UNIT NO. 1 AMENDMEllT TO FACILITY OPERAT1t!G LICENSE Amendment flo. 3 License No NPF-86 1.

The Nuclear Regulatory Commission (the Commission or the NRC) has found that:

A.

The application for amendment filed by the Public Service Company of New Hampshire (the licensee), acting for itself and as agent and representative of the 11 other utilities listed below and hereafter referred to as licensees, dated January 24, 1991 as supplemented by letter dated May 16, 1991 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.

The issuance of this amendrent will not be inimical to the common defense and security or to the health and s ty of the public; and E.

The issuance of this amendment is in accordant, sith 10 CFR Part 51 of the Conmission's regulations and all applicable requirements have been satisfied.

Public Service C~pany of New Hampshire is authorized to act as agent for the:

Canal Electric Cuupany, The Connecticut Light and Power Comrsny, EUA Power Corporation, Hudson Light & Power Department, Massachusetts Municipal Wholesale Electric Company, Montaup Electric Company, New England Power Company, tiew Hampshire Electric Cooperative, Inc., Taunton Municipal Light Plant, The United 111uminating Company, and Vermont Electric Generation and Transmission Cooperative, Inc., and has exclusive responsibility and t.ontrol over the physical construction, operation and maintenance of the f acility.

9107260217 910715 PDR ADOCK 05000443 P

PDR

2 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of f acility Operating License No. NPF-86 is hereby amended to read as follows:

(2) T,echnj cal,,Specifica tions The Technical Specifications contained in Appendix A, as revised through Amendment No. 3, and the Environmental Protection Plan contained in Appendix B are incorporated into facility Operating License No. HPF-86. PSNH shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of its date of issuance and shall be implemented prior to restart from the first refueling outage.

FOR THE NUCLEAR REGULATORY COMMISSION o,1 chard H. Wessman, Directo Project Directorate 1 3 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

July 15, 1991 a

l 1

)

ATTACHMENT TO LICENSE AMENDMENT NO. 3 FACILITY OPERATING LICENSE NO. NPF-86 I

DOCKET NO.,50,,4_43 Replace the following pages of the Appendix A Technical Specifications with the attached pages.

The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. Overlap pages are provided for continuity.

l Remove Insert

-774'4!34 3/4 4 34 3/4 4 35 3/4 4-35 3/4 5-6 3/4 5 6 B3/4 4-15 B3/4 4-15 B3/4 4 16 B3/4 4-16 B3/4 4-17*

h 1

Denotes new page

l REACTOR COOLANT SYSTEM PRES $URE/ TEMPERATURE LIMITS PRESSJRIZER L'AITING CON 0! TION FOR OPERATION 3.4.9.2 The pressurizer temperature shall be limited to:

a.

A maximum heutup of 100'F in any 1-hour period, b.

A maximum cooldown of 200'F in any 1-hour period, and c.

A maximum spray water temperature differential of 320*F.

APPLICABILITY:

At all times.

ACTION:

With the pressurizer temperature limits in s' cess of any of the above limits, restore the temperature to within the limits within 30 minutes; perform an engineering evaluation to determine the effects of the out-of-limit condition on the structural integrity of the pressurizer; determine that the pressurizer remains acceptable for continued operation or be in at least HOT STANDBY within

-the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and reduce the pressurizer pressure to less than 500 psig within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.4.9.2 The pressurizer temperatures shall be determined to be within the limits at least once per 30 minutes during system heatup or cooldown.

The spray water temperature differential shall be determined to be within the limit at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during auxiliary spray operation.

SEABROOK UNIT 1 3/4 4-33 I

1 REACTOR COOLANT SYSTEM PRESSUREf@PERATURELIMITS OVERPRESsStE PROTECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.9.3 At least one of the following Overpressure Protection Systems shall be OPERABLE:

a.

Two residual heat removal (RHR) suction relief valves each with a setpoint of 450 psig +0, -3 %; or b.

Two power-operated relief valves (PORVs) with lift setpoints that vary with RCS temperature which do not exceed the limit established in Figure 3.4-4, or c.

The Reactor Coolant System (RCS) depressurized with r,9 RCS vent of greater than or equal-to 1.58 square inches.

APPLICABILITY:

MODE 4 when the tremperature of any RCS cold leg is less than or equal to 329'F; MODE 5 and MODE 6 with the reactor vessel head on.

ACTION:

a.

With one PORV and one RHR suction relief valve inoperable, either restore two PORVs or two RHR suction relief valves to OPERABLE status within 7 days or depressurize and vent the RCS through at least a 1.58 square-inch vent within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , b.

With both PORVs and both RHR suction relief valves inopt:rable depressurizeandventtheRCSthroughatleasta1.58-square-Inch vent within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

c.

In the event the PORys, or the RHR suction relief valvns, or the RCS vent (s) are used to mitigate an RCS pressure transient, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.8.2 within 30 days.

The report shall describe the circumstances initiating the transitnt, the effect of the PORVs, or the RHR suction relief valves, or RCS vent (s) on the transient,-and any corrective action necessary to prevent recurrence.

SEABROOK - UNIT 1 3/4 4-34 Amendment No. 3

e REACTOR COOLANT SYSTEM PRESSURE / TEMPERATURE LIMITS OVERPRES$URE PROTECTION SYSTEMS SURVCILLANCE REQUIREMENTS 4.4.9.3.1 Each PORV shall be demonstrated OPERABLE by:

a.

Performance of an ANALOG CHANNEL OPERATIONAL TEST on the PORV actuation channel, but excluding valve o>eration within 31 days priortoenteringaconditioninwhicht1ePORYIsrequiredOPEPABLE and at least once per 31 days thereafter when the PORV is required OPERABLE; b.

Performance of a CHANNEL CALIBRATION on the PORV actuation channel at least once per 18 months; and c.

Verifying the PORV isolation valve is open at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months when the PORV is being used for overpressure protection.

4.4.9.3.2 Each RHR suction relief valve shall be demonstrated OPERABLE when the RHR suction relief valves are being used for cold overpressure protection-as follows:

a.

For RHR suction relief valve RC-V89 by verifying at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months that RHR suction isolation valves RC-V87 and RC-V88 are

open, b.

For RHR suction relief valve RC-V24 by verifying at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months that RHR suction isolation valves RC-V22 and RC-V23 are open.

c.

Testing pursuant to Specification 4.0.5.

4.4.9.3.3 The RCS vent (s) shall be verified to be open at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

when the vent (s) is being used for overpressure protection.

Except when the vent pathway is provided with a valve that is locked, sealed, or otherwise secured in the open position, then verify these valves open at

-least once per 31 days.

SEABROOK - UNIT 1 3/4 4-35 Amendment No. 3..

I e

0 e*

f se m's W

N T

I o

3 o

W I

N a

e i

I Mk N

w l

l l

O g

o ee

1 h

M.-

uN w

w

_.L -

b o

I W

dW

- +(

K 4

D W

e ce k

8 4

D 0O K

^

\\

-r d

I

)'

w ce 2

A l

\\

Y Y

Y s

g_x@

g....

M O

}

I o

y g

o 8

i t

w l

.3 m

O J

cs I

Q g

@gg

_... _.q;.

3 1

y o

o m

4 t-.pg'3 <--

O 1

z w

d --

g

- _,. n l

O l

... g E y g

_w.

>ve I

1

.o O

O O

O eft Q

tfl O

ett N

N N

(oise) miosus Avos nnnixvn SEABROOK - UNIT 1 3/4 4-36

EMERGENCY CORE COOLING SYSTEMS ECCS SUS $YSTEMS - T,y GREATER THAN OR EQUAL TO 350*F SURVEILLANCE REQUIREMENTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying that the following valves a.

are in the indicated positions with power to the valve operators removed:

Valve Number Valve Function Valve Position SI-V-3 Accumulator Isolation Open*

SI-V 17 Accumulator Isolation Open a SI-V-32 Accumulator Isolation Open*

SI-V-47 Accumulator Isolation Open*

SI-V-114 SI Pump to Cold-Leg Isolation Open RH-V-14 RHR Pump to Cold-Leg Isolation Open RH-V-26 RHR Pump to Cold-Leg Isolation Open RH-V-32 RHR to' Hot-Leg Isolation Closed RH-V-70 RHR to Hot-Leg Isolation Closed SI-V-77 SI to Hot-Leg Isolation Closed SI-V-102 SI to Hot-Leg Isolation Closed

'b.

At least once per 31 days by:

1)

Verifying that the ECCS piping is full of water by venting the ECCS pump casings and accessible discharge piping high points, and 2)

Verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealed. or otherwise secured in position, is in its correct pasition.

c.

By a visual inspection which verifies that no loose debris (rags, trash, clothi % etc.) is present in the containment which could be transported

s. the containment sump and cause restriction of the pump suctions during LOCA conditions.

This visual inspection shall be performed:

1)

For all-accessible areas of the containment prior to establish-ing PRIMARY CONTAINMENT INTEGRITY, and 2)

Of the areas affected within containment at the completion of each containment entry when PRIMARY CONTAINMENT INTEGRITY is established.

Pressurizer pressure above 1000 psig.

SEA 8 ROOK - UNIT 1 3/4 5-5

EMERGENCY CORE COOLING SYSTEMS ECCS SUBSYSTEMS - T,yg GREATER =THAN OR EQUAL TO 350'F SURVEILLANCE REQUIREMENTS 4.5.2 (Continued) d.

At least once per 18 months by:

1)

Verifying automatic interlock action of the RHR system from the Reactor Coolant System to ensure that with a simulated or actual Reactor Coolant System pressure signal greater than or equal to 365 psig, the interlocks prevent the valves from being opened.

2)

A visual inspection of the containment sump and verifying that the subsystem suction inlets are not restricted by debris and that the sump components (trash racks, screens, etc.) show no evidence of structural distress or abnormal corrosion, e.

At least once per 18 months, during shutdown, by:

1)

Verifying that each automatic valve in the flow path actuates to its correct position on (Safety Injection actuation and Automstic Switchover to Containment Sump) test signals, and 2)

Verifying that each of the followin? pumps start automatically upon receipt of a Safety Injection actuation test signal:

a)

Centrifugal charging pump, b)

Safety Injection pump, and c)

RHR pump, f.

By verifying that each of the following pumps develops the indicated differential pressure on recirculation flow when tested pursuant to Specification 4.0.5:

1)

Centrifugal charging pump, 1 2480 psid; 2)

Safety Injection pump, t 1445 psid; and 3)

RHR pump, > 176 psid.

SEABROOK - UNIT 1 3/4 5-6 Amendment No. 3

REACTOR COOLANT SYSTEM BASES 3/4.4.9 PRESSURE / TEMPERATURE LIMITS (Continued)

COLD OVERPRESSURE PROTECTION The OPERABILITY of two PORVs, or two RHR suction relief valves, or an RCS vent opening of at least 1.58 square inches ensures that the RCS will be protected from pressure transients which could exceed the limits of Appenix G to 10 CFR Part 50 when one or more of the RCS cold legs are less than or equal to 329'F.

Either PORV or either RHR suction relief valve has adequate relieving capability to protect the RCS from overpressurization when the transient is limited to either:

(1) the start of an idle RCP with the secondary water temperature of the steam generator less than or equal to 50'F above the RCS cold leg temperatures, or (2) the start of a centrifugal charging pump and its injection into a water-solid RCS.

The Maximum Allowed PORV Setpoint for the Cold Overpressure Hitigation System (COMS) is derived by analysis which models the performance of the COMS assuming various mass input and heat input transients.

Operation with a PORV Setpoint less than or equal to the maximum Setpoint ensures that Appendix G criteria will not be violated with consideration for:

(1) u maximum pres-sure overshoot beyond the PORV Setpoint which can occur as a result of time de-lays in signal processing and valve opening; (2) a 50'F heat transport effect made possible by the geometrical relationship of the RHR suction line and the RCS wide range temperature indicator used for COMS; (3) instrument uncertain-ties; and (4) single failure.

To ensure mass and heat input transients more severe than those assumed cannot occur, Technical Specifications require lock-out of both Safety Injection pumps and all but one centrifugal charging pump while in MODES 4, 5, and 6 with the reactor vessel head installed and disallow start of an RCP if secondary coolant temperature is more than 50*F above reac-tor coolant temperature.

Exceptions to these requirements are acceptable as described below.

Operation above 350*F but less than 375 F with only centrifugal charging pump OPERABLE and no Safety Injection pumps OPERABLE is alicwed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

As shown by analysis, LOCAs occurring at low temperature, low pres-sure conditions can be successfully mitigated by the operation of a single centrifugal charging pump and a single RHR pump with no credit for accumulator injection.

Given the short time duration and the condition of having only one contrifugal charging pump OPERABLE and the probability of a LOCA occurring dur-ing this time, the failure of the single centrifugal charging pump is not assumed.

Operation below 350'F but greater than 325'F with all centrifugal charging and Safety Injection pumps OPERABLE is allowed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

During low pressure, low temperature operation all automatic Safety Injection actuation signals except Cnntainment Pressure - High are blocked.

In normal conditions, a single failure of the ESF actuation circuitry will result in the starting of atmostonetrainofSafetyInjection(onecentrifugalchargingpump,andone Safety Injection pump).

For temperatures above 325 F, an overpressure event occurring as a result of starting two pumps can be successfully mitigated by N rk Nnt b 3

l REACTOR C00LANT SYSTEM BASES 3/4.4.9 PRESSURE / TEMPERATURE LIMITS (Continued)

COLD OVERPRESSURE PROTECTION (Continued) operation of both PORVs without exceeding Appendix G limit.

Given the short i

time duration that this condition is allowed and the low probability of a single failure of a PORV is not assumed.

Initiation of bcth trains of Safety Injection during this 4-hour time frame due to operator error or a single fail-ure occurring during testing of a redundant enannel are not considered to be credible accidents.

Operation with all centrifugal charging pumps and both Safety In pumsOPERABLEisacceptablewhenRCStemperatureisgreaterthan350jection F, a sin le PORV has sufficient capccity to relieve the combined flow rate of all pumps.

Above 350'F two RCPs and all pressure safety valves are required to be OPERABLE.

Operation of an RCP eliminates the possibility of a 50'F difference existing between indicated and actual RCS temperature as a result of heat trans-port effects.

Consioectig instrument uncertainties only, an indicated RCS tem-perature of 350*F is sufficiently high to allow full RCS pressurization in ac-cordance with Appendix G limitations.

Should an overpressure event occur in these conditions, the pressurizer safety valves provide acceptable and redun-dant overpressure protection.

The Maximum Allowed PORV Setpoint for the Cold Overpressure Mitigation System will be revised on the basis of the results of examinathns of rector vessel material irradiation surveillance specimens performed at' required by 10 CFR Part 50, Appendix H.

3/4.4.10 STRUCTURAL INTEGRITY The inservice inspection and testing programs for ASME Code Class 1, 2, and 3 components ensure that the structural integrity and operational readiness of these components will be maintained at an acceptable level throughout the life of the olant.

These programs are in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50.55a(g) except where specific written relief has been granted by the Commission pursuant to 10 CFR 50.55a(g)(6)(1).

Components of the Reactor Coolant System were designed to provide access to permit inservice inspections in accordance with Section XI of the ASME Boiler and Pressure Vessel Code, 1983 Edition and Addenda through Summer 1983.

SJE,B7 ment ifo.b 0K '

n

REACTOR COOLANT SYSTEM BASES 3/4.4.11 REACTOR COOLANT SYSTEM VENTS Reactor Loolant System vents are provided to exhaust noncor.densible gases Ind/or steam from the Reactor Coolant System that could inhibit natural circu-lation core ccoling.

The OPERABILITY of least one Reactor Coolant System vent path from the reactor vessel head and the pressurizer steam space ensurer that the capability exists to perform this function.

The valve redundancy of the Reactor Coolant System vent paths serves to minimize the probability of inadvertent or irreversible actuation while ensuring that a single failure of a vent valve, power supply, or control system does not prevent isolation of the vent path.

The function, capabilities, and testing requirement. of the Reactor Coolant System vents are consistent with the requirements of Item II.B.1 of NUREG-0737,

" Clarification of TMI Action Plant Requirements," November 1980.

e SEABROOK - UNIT 1 B 3/4 4-17 A endment No. 3

ML20085A753

Text

Attachment:

Navigation menu

Search