Text

Amend 36 to License NPF-47,modifying Tech Spec 3.0.4 to Allow Entry Into Specified Operational Conditions W/O Meeting Limiting Condition for Operation,Provided Requirements of Associated Action Statements Met
	ML20235Z101
Person / Time
Site:	River Bend
Issue date:	03/03/1989
From:	Calvo J; Office of Nuclear Reactor Regulation
To:	;
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ML20235Z104	List: ML20235Z101; ML20235Z107;
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8 UfdlTED STATES

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GULF STATES UTILITIES COMPANY DOCKET NO. 50-458 RIVER BEND STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.36 License No. NPF-47 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Gulf States Utilities Company dated December 16, 1988, as modified January 24, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

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

There is reasonable assurance:

(1) 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 conipliance with the Comission's regulations; D.

The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

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 Facility Operating License No. NPF-47 is hereby amended to read as follows:

(2) Technical Specifications and Environmental Protection Plan l

The Technical Specifications contained in Appendix A, as revised through Amendment No. 36 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. GSU shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

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The license amendment is effective as of its date of issuance.

FOR THE NUCLEAR' REGULATORY COMMISSION rj 4, gcf%,

[JoseA.Calvo, Director Project Directorate - IV Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: March 3, 1989

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ATTACHFENT TO LICENSE AMENDMENT fl0. 36 FACILITY OPERATING LICENSE NO. NPF-47 DOCKET N0. 50-458 Replace the following paget of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain a vertical line indicating the area of change. Overleaf page provided to maintain document completeness.

REMOVE PAGES INSERT PAGES 3/4 4-29 3/4 4-29 3/4 7-5 3/4 7-5 3/4 9-18 3/4 9-18

REAC' TOR COOLANT SYSTEM COLD SHUTDOWN 2

LIMITING CONDITION FOR OPERATION 3.4.9.2 Two# shutdown cooling mode loops of the residual heat removal (RHR) system shall be OPERABLE and, unless at least one recirculation pump is in operation, at least one shutdown cooling mode loop shall be in operation *,##

with each loop consisting of at least:

)

a.

One OPERABLE RHR pump, and b.

Two OPERABLE RHR heat exchangers.

APPLICABILITY:

OPERATIONAL CONDITION 4.

ACTION:

a.

With less than the above required RHR shutdown cooling mode loops OPERABLE, within one hour and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter demonstrate the operability of at least one alternate method capable of decay heat removal for each inoperable RHR shutdown cooling mode loop.

b.

With no RHR shutdown cooling mode loop or recirculation pump in opera-tion, within one hour establish reactor coolant circulation by an alternate method and monitor reactor coolant temperature and pressure at least once per hour.

c.

The provisions of Specification 3.0.4 are not applicable.**

l SURVEILLANCE REQUIREMENTS 4.4.9.2 At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , at least one shutdown cooling mode loop of the residual heat removal system, one recirculation pump or alternate method shall be determined to be in operation and circulating reactor coolant.

0ne RHR shutdown cooling mode loop may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing provided the other loop is OPERABLE and in operation or at least one recirculation pump is in operation.

The shutdown cooling pump may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period provided the other loop is OPERABLE.

1. The shutdown cooling mode loop may be removed from operation during hydrostatic testing.

- This exception is applicable until startup from the second refueling outage.

RIVER BEND - UNIT 1 3/4 4-29 Amendment No.36

PLANT SYSTEMS 3/4.7.2 MAIN CONTROL ROOM AIR CONDITIONING SYSTEM LIMITING CONDITION FOR OPERATION 3.7.2 The main control room air conditioning system, with two independent air handling unit / filter train subsystems, shall be OPERABLE.

APPLICABILITY:

All OPERATIONAL CONDITIONS and *.

ACTION:

a.

In OPERATIONAL CONDITION 1, 2 or 3 with one main control room air conditioning subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

In OPERATIONAL CONDITION 4, 5 or *:

3.

With one main control room air conditioning air handling / filter train subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 7 days or initiate and maintain operation of the OPERABLE subsystem in the emergency mode of operation.

2.

With both main control room air conditioning air handling / filter train subsystems inoperable, suspend CORE ALTERATIONS, handling of irradiated fuel in the primary containment and Fuel Building and operations with a potential for draining the reactor vessel.

3.

The provisions of Specification 3.0.4 are not applicable.#

c.

The provisions of Specification 3.0.3 are not applicable in Operational Condition *.

SURVEILLANCE REQUIREMENTS 4.7.2 Each main control room air conditioning subsystem shall be demonstrated OPERABLE:

a.

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that the control room air temperature is less than or equal to 104*F.

b.

At least once per 31 days on a STAGGERED TEST BASIS by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the subsystem operates for at least 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months with the heaters OPERABLE.

When irradiated fuel is being handled in the primary containment or Fuel Building.

This exception is applicable until startup from the second refueling outage.

l RIVER BEND - UNIT 1 3/4 7-5 Amendment No.36

a PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) c.

At least once per 18 months ~or-(1) after' any structural maintenance '

on the HEPA. filter or charcoal adsorber housings, or (2) following painting.. fire or chemical release in any ventilation zone communi-cating with the subsystem by:

1.

Verifying that the subsystem satisfies the in place penetration 2

and bypass leakage testing acceptance criterion of less than 0.05% and uses the test procedure guidance in Regulatory Post-tions C.5.a. C.S.c and C.5.d of Regulatory Guide 1.52, Revision-2, March 1978, and the system flow rate is-4000 cfm i 10%.

2.

Verifying within 31 days after removal that a laboratory' analysis i

of a representative carbon sample obtained in accordance with '

Regulatory Position C.6.b of Regulatory Guide 1.52. Revision 2 March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2. March 1978, for a methyl iodide penetration of less than 0.1M %; and' 3.

Verifying a subsystem flow rate of 4000 cfm i 10% during sub-system operation when tested in accordance with ANSI N510-1980.

d.

Afterl every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of' charcoal adsorber operation by verifying within 31 days after removal that a laboratory analysis of a repre-sentative carbon sample obtained in accordance with Regulatory Posi-ton C.6.b of Regulatory Guide 1.52, Revision 2. March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978, for a methyl iodide-penetration of less than 0.175%.

e.

' At least once per 18 months by:

1.

Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 8 inches water ~ gauge while operating the subsystem at a flow rate of 4000 cfm i 10%.

2.

Verifying that on each of the'below emergency mode actuation test signals, the, subsystem automatically switches to the emergency mode of operation, the isolation valves close within 30 seconds, and the control room is maintained at a positive pressure of > 1/8 inch water gauge relative to the outside atmosphere during subsystem operation at a flow rate less than or equal to 4,000 cfs:

- a)

LOCA, and l

b)

' Local air intake radiation monitor - High.

3.

Verifying that the heaters dissipate 2312.3 kw when tested in accordance with ANSI N510-1980, at the design supply voltage.

""Ihe specified 18 month interval during the first operating cycle may be extended to coincide with completion of the first refueling outage, scheduled to begin 9-15-87.

RIVER BEND - UNIT 1 3/4 7-6 Amendment No.It I

4

REFUELING OPERATIONS LOW WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.11.2 Two shutdown cooling mode loops of the residual heat removal (RHR)

I system shall be OPERABLE and at least one loop shall be in operation,* with I

each train consisting of at least:

a.

One OPERABLE RHR pump, and b.

Two OPERABLE RHR heat exchangers.

APPLICABILITY:

OPERATIONAL CONDITION 5, when irradiated fuel is in the reactor vessel and the water level is less than 23 feet above the top of the reactor pressure vessel flange.

ACTION:

a.

With less than the above required shutdown cooling mode loops of the RHR system OPERABLE, within one hour and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter, demonstrate the operability of at least one alternate method capable of decay heat removal for each inoperable RHR shutdown cooling mode train.

With no HR shutdown cooling mode loop in operation, within one hour b.

R establish reactor coolant circulation by an alternate method, and monitor reactor coolant temperature at least once per hour, c.

The provisions of Specification 3.0.4 are not applicable.**

j SURVEILLANCE REQUIREMENTS 4.9.11.2 At least one shutdown cooling mode loop of the residual heat removal system or alternate method shall be verified, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , to be in operation and circulating reactor coolant.

"The shutdown cooling pump may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8-hour period.

- This exception is applicable until startup from the second refueling outage.

l RIVER BEND - UNIT 1 3/4 9-18 Amendment No. 36

REFUELING OPERATIONS 3/4.9.11 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION HIGH WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.11.1 At least one shutdown cooling mode loop of the residual heat removal (RHR) system shall be OPERABLE and in operation

with at least:

a.

One OPERABLE RHR pump, and b.

Two OPERABLE RHR heat exchangers.

APPLICABILITY:

OPERATIONAL CONDITION 5, when irradiated fuel is in the reactor vessel and the water level is greater than or equal to 23 feet above the top of the reactor pressure vessel flange.

ACTION:

a.

With no RHR shutdown cooling mode OPERABLE, within one hour and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter, demonstrate the operability of at least one alternate method capable of decay heat removal. Otherwise, suspend all operations involving an increase in the reactor decay heat load and establish PRIMARY CONTAINMENT INTEGRITY - FUEL HANDLING within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , b.

With no RHR shutdown cooling mode loop in operation, within one hour establish reactor coolant circulation by an alternate method, and monitor reactor coolant temperature at least once per hour.

SURVEILLANCE REQUIREMENTS 4.9.11.1 At least one shutdown cooling mode loop of the residual heat removal system or alternate method shall be verified, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , to be in operation and circulating reactor coolant.

The shutdown cooling loop may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8-hour period.

l RIVER BEND - UNIT 1 3/4 9-17

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