ML20134G592

Proposed Tech Specs 3.13.1.A Re Limiting Operation for Operation

ML20134G592
Person / Time
Site:	Zion  File:ZionSolutions icon.png
Issue date:	11/07/1996
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20134G585	List: ML20134G582 ML20134G592
References
NUDOCS 9611130287
Download: ML20134G592 (13)

Text

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l ATTACIIMENT H ZION NUCLEAR GENERATING STATION I

MARKED UP ANNOTATED COPY OF TECIINICAL SPECIFICATIONS FACILITY OPERATING LICENSES DPR-39 AND DPR-48 APPENDIX A TECllNICAL SPECIFICATIONS RIIR REQUIREMENTS DURING CORE ALTERATION OPERATIONS l

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I 9611130297 961107 PDR ADOCK050002]5 P

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LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENTS 3.13.1.A (Continued) 4.13.1.A (Continued)

3. The movement of an irradiated fuel 3. Not applicable.

assembly in the reactor core shall not begin until the reactor has been subcritical for a period of at least 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />. .

4. A least one RHR pump and heat 4. The operation of at hast one aHR exchanger shall be in operation during pump and heat exchanger shall be core alteration operations, epsspta.s verifled once a shiftjspc y r *,r +t. sg

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5. Q M 3. 1. B . 4 .

Direct connunication between the 5. Communication between the control control room and containment shall be room and the containment shall be OPERABLE.

verified before any alteration of

, the reactor core begins.

6. A licensed fuel handling foreman or 6. Not applicable.

licensed senior reactor operator shall '

be present at the reactor cavity during any movement of fuel within the containment.

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. Amendment Nos'. 96 and 86 09150/09180 788

LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENTS 3.13.1.A (Continued) 4.13.1.A (Continued) -

3. The movement of an irradiated fuel assembly in 3. Not applicable.

the reactor core shall not begin until the reactor has been suberitical for a period of at least 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />.

4. At least one RHR pump and heat exchanger shall 4. The operation of at least one RHR pump and be in operation during core alterations heat exchanger shall be verified once a shift, ~

operations, except as allowed by 3.13.9.B.b. except as allowed by 3.13.9.B.b.

5. Dirs t communication between the control room 5. Communication between the control room and the and containment shall be OPERABLE. containment shall be verified before any alteration of the reactor core begins.

6. A licensed fuel handling foreman or licensed 6. Not appl'icable.

senior reactor operator shall be present at the reactor cavity during any movement of fuel within the containment.

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244 Amendment Nos. 96 and 86

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.f SURVEILLANCE REQUIREE NT LIMITING CONDITION FOR OPERATION -

4.13.9.B  !

3.13.9.8 N _

10. Water Level - Reactor Vessel

b. The residual heat removal loop may be removed from operation for up to one hour A. The water level shall be  !

I per an eight-hour period during the '

determined to be at or above perfonnance of CORE ALTERATIONS. the minimum required depth  ;

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within two hours prior to

10. Water Level . Reactor Vessel the start of fuel movements.

At least once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> A. At least 22 feet of water shall be throughout movement of futi maintained over the top of the s assemblies or control rods, reactor pressure vessel flange. \ , the required water depth .

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shall be detemined to be

• Applicability: at or-above the minimum depth.

During sevement of fuel assemblies or control rods

• within the reactor pressure vessel while in MODE 6. .

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With the requirements of the above i specification not satisfied, suspend [a /- f e [e/*67/c C O///v ,/ '

all operations involving movement of fuel assemblies or control rods /

within the pressure vessel.

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• Except during control ved latching operations .

l wherein the water level shall be 22 feet above the seated fuel assemblies in the reactor core.

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. 247c Amendment Mos. 718 65

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l SURVEf f.I.ANCE RE(4filtEMENT l I,1HITING CC:DITION IOR OPERATION --

4.13 9. A.

e'3.13 9.A.

ACTION: a. With less than the required RIIR loops OPER AD E,E , immediately initiate corrective action to return the required ItitR loops to OPERAn!,E status as soon as possible.

b. With no rentdual heat removal loop in operation, suspend all operations that ^

would cause~ a decrease in decay heat  !

removal capaht11 ties or a reduction in boron concentration of the Reactor ,

Coolant System. Close all containment penetrations providing direct access f rom the containment atmosphere to the outside atmosphere within four hours. .

D. At least one Residual lleat Removal loor 3 B. At least one residual heat removal (RifR) shall be verified to be OPERATING and loop shall be OPERATING. .

c irculating re.ictor coolant at 1 cast once per shif t.

AI'PI,1 CAD II,1TY : Mode G when the water level above the top of the reactor pressure vessel flange is greater than 22 f t.

• , ni)::: a. With no residual heat removat loop in 'm'

. operation, except as provided in b.

below, suspend all operations that would '

cause a decrease in decay heat removal capabL11tles or a reducti'on in boron concentration of the Reactor Coolant Systemyg cglose all contsinment pene attons providing direct access from e containment atmosphere to the outside atmosphere within f our hours.

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c o s. ( o f f d a. 6 0 sr.r, s ,,hoe /,j Amendment Nos. 65 & 62

LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.13.9.A. 4.13.9.A.

ACTION: a. With less than the required RHR loops OPERABLE, bnmediately initiate corrective action to return the required RHR loops to OPERABLE status as soon as possible.

b. With no residual heat removal loop in operation, suspend all operations that would cause a decrease in decay heat f- .

removal capabilities or a reduction in boron concentration of the Reactor Coolant System. Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within four hours.

l B. At least one residual heat removal (RHR) loop B. At least one Residual Heat Removal loop shall be OPERATING. shall be verified to be OPERATING and circulating reactor coolant at least APPLICABILITY: Mode 6 when the water level above once per shift.

the top of the reactor pressure vessel flange is greater.than 22 ft. .

ACTION: a. With no residual heat removal loop in

. operation, except as provided in b.

below, suspend all operations that would [~h '

cause a decrease in decay heat removal capabilities or a reduction in boron concentration of the Reactor Coolant ,

System. If RHR has been out of operation for greater than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, suspend core alterationsf and close all containment penetretions providing direct access from the containment atmosphere to the outside atmosphere within four hours.

i 247b Amendment Nos. 65 and 62

Ccccas 3.13 .

The verification of fuel handling system interlocks The restriction on shutdown margin insures adequate core protection that no inadvertent return to prior to refueling operation provides assurance that criticality could occur through control rod an unsafe operating condition will not be approved. (1) removal. (1) The fuel inspection program is intended to provide Two source range neutron monitors continuously information on anomalous conditions of the fuel resulting from power operation. The results of the measuring neutron flux during fuel movements provides the operators with immediate redundant visual examinations and the tests for failed fuel will be reviewed as a basis for determining the indication of an unsafe condition. Whenever requirements for further off-site destructive fuel changes are not being made in the core geometry, FSAR Section 3.2.3.5 provides further one flux monitor is sufficient. This permits examinations.

discussion of the fuel inspection program.

maintenance on the instrumentation.

The fuel handling accident assumes that the first The requirement that at least one residual heat fuel assembly is moved 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> after initial removal (RHR) loop be in operation ensures that (a) sufficient cooling capacity is available to remove reactor shutdown. (2) decay heat and maintain the water in the reactor Direct communication between the control room and pressure vessel below 140*F as required during the REFUELING MODE, and (b) sufficient coolant circulation is the containment allows for immediate notification maintained through the reactor core to minimize the

~ of any impending unsafe condition.

,' effect of a boron dilution incident and prevent baron The presence of a licensed fuel handling foreman or stratification. 74e g//g/,y pe.

senior reactor operator at the refueling cavity ys/ =,2%#1 [o A ye 2'a ar/an 4gner a.ye/90df efg /4, ppg /e 4.,g c,ff provides qualified supervision on the refueling The requirement to have two RHR loops OPERABLE when there is less than 22 feet of water above the flange ensures operation during changes in core geometry. that a single failure of the operating RHR loop will not result in a complete loss of residual heat removal

.-- The charcoal filters in the ventilation train f rom capability. With the reactor vessel head removed and 22 the fuel building insure that site boundary doses feet of water above the flange a large heat sink is will be below 10 CFR 100 limits as'suming all rods available for core cooling. Thus, in the event of a on a dropped fuel assembly break during a failure of the operating RHR loop, adequate time is postulated fuel assembly break during a postulated fuel drop accident. (3) The containment, fuel provided to initiate emergency procedures to cool the core, building, and radiation monitoring requirements insure the capability to isolate these areas from the environment in the event of an activity release A minimum water level of 22 feet over irradiated assemblies ensures that sufficient water depth is from the fuel. available to remove 99% of the assumed 10% iodine gap activity released from the rupture of an irradiated fuel assembly. A 23 feet depth over fuel in the Spent Fuel FSAR, Section 9.7.2 Pool corresponds to 22 feet of water over the pressure g (1) vessel flange. The control rod latching operations are l (2) FSAR, Section 14.2.1.2 FSAR, Section 14.2.1.5 conducted with at least the minimum water level over (3) seated assemblies.

248 Amendment Nos. 71 and 65

Cteso: 3.13 The verification of fuel handling system interlocks The restriction on shutdown margin insures adequate core protection that no inadvertent return to prior to refueling operation provides assurance that criticality could occur through control rod an unsafe operating condition will not be approved. (1)s removal. (1) The fuel inspection program is intended to provide Two source range neutron monitors continuously information on anomalous conditions of the fuel measuring neutron flux during fuel movements resulting from power operation. The results of the provides the operators with immediate redundant visual examinations and the tests for failed fuel will be reviewed as a basis for determining the indication of an unsafe condition. Whenever requirements for further off-site destructive fuel changes are not being made in the core geometry, FSAR Section 3.2.3.5 provides further examinations.

one flux monitor is sufficient. This permits discussion of the fuel inspection program.

maintenance on the instrumentation.

The fuel handling accident assumes that the first The requirement that at least one residual heat fuel assembly is moved 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> after initial removal (RHR) loop be in operation ensures that (a) sufficient cooling capacity is available to remove reactor shutdown. (2) decay heat and maintain the water in the. reactor Direct communication between the control room and pressure vessel below 140*F as required during the REFUELING MODE, and (b) sufficient coolant circulation is the containment allows for immediate notification maintained through the reactor core to minimize the of any impending unsafe condition.

' effect of a boron dilution incident and prevent boron stratification. The RHR loop may be taken out of The presence of a licensed fuel handling foreman or operation for up to one hour in an eight hour period.

senior reactor operator at the refueling cavity provides qualified supervision on the refueling - The requirement to have two RHR loops OPERABLE when there operation during changes in core geometry.

is less than 22 feet of water above the flange ensures

-~The charcoal filters in the ventilation train from that a single failure of the operating RHR loop will not the fuel building insure that site boundary doses result in a complete loss of residual heat removal will be below 10 CFR 100 limits assuming all rods capability. _ With the reactor vessel head removed and 22 on a dropped fuel assembly break during a feet of water above the flange a large heat sink is available for core cooling. Thus, in the event of a postulated fuel assembly break during a postulated failure of the operating RHR loop, adequate time is fuel drop accident. (3) The containment, fuel building, and radiation monitoring requirements provided to initiate emergency procedures to cool the insure the capability to isolate these areas from core.

the environment in the event of an activity release from the fuel.

A minimum water level of 22 feet over irradiated assemblies ensures that sufficient water depth is available to remove 99% of the assumed 10% iodine gap activity released from the rupture of an irradiated fuel FSAR, Section 9.7.2 assembly. A 23 feet depth over fuel in the Spent Fuel (1) Pool corresponds to 22 feet.of water over the pressure gll (2) FSAR, Section 14.2.1.2 vessel flange. The control rod latching operations are (3) FSAR, Section 14.2.1.5 conducted with at least the minimum water level over seated assemblies.

n-e-a-one nna. 71 and 65

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J ATTACilMENT C l 7lON NUCLEAR GENERATING STATION EVALUATION OF SIGNIFICANT ll AZARD CONSIDERATIONS FOR PROPOSED CilANGES TO i FACILITY OPERATING LICENSES I DPR-39 AND DPR-48 APPENDIX A TECIINICALSPECIFICATIONS l l

l RilR REQUIREMENTS DURING CORE ALTERATION OPERATIONS i

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4 Conunonwealth Edison has evaluated this proposed license amendment and determined that it involves i no significant hazard considerations. According to 10 CFR 50.92(c), a proposed amendment to an operating license involves no significant hazard considerations if operation of the facility in accordance with the proposed amendment would not:

1. Involve a significant increase in the probability of occurrence or consequences of an accident previously evaluated;

2. Create the possibility of a new or different kind of accident from any previously analyzed; or, i

3. Involve a significant reduction in the margin of safety.

This determination has been performed as indicated below:

1. The proposed changes do not involve a significant increase in the probability or consequences of occurrence of any accident previously evaluated.

The ability to remove an RHR loop from operation for up to one hour per eight-hour period is currently allowed by technical specification 3.13.9.B.b. By adding a reference to LCO 3.13.1.A.4. and adding the requirement to suspend CORE ALTERATIONS to Action i 3.13.9.B.a. to be consistent with 3.13.9.B.b, no change in operating practices or plant i configuration is made. By maintaining the requirement to have an RHR loop in operation j during MODE 6, and by requiring CORE ALTERATIONS to be suspended if an RHR loop is not back in operation afler one hour, adequate corrective actions are implemented until the RHR loop is restored to operating status. Therefere, operation of the system is consistent with current technical specifications and this change does not involve a significant increase in the probability or consequences of an accident previously evaluated

2. The proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated.

The proposed changes do not require a physical alteration of the plant (no new or different equipment will be installed to implement this change). The Technical Specifications will continue to require an RHR loop to be in operation during MODE 6, and will only pennit the loop to be not in operation for up to one hour in an eight-hour period. The Technical Specifications will continue to require compliance with these limitations and suspension of CORE ALTERATIONS if an RHR loop is not in operation for more than one hour. Thus, this change does not create the possibility of a new or difTerent kind of accident from any accident previously evaluated.

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3. The proposed changes do not involve a significant reduction in a margin of safety.

The proposed changes do not result in a significant reduction in a margin of safety because it i has no impact on any safety analysis assumptions. The requirement to have an RHR loop in 1 operation during MODE 6 is maintained, along with the ability to remove RHR from operation 7 for up to one hour per eight-hour period. If an RHR loop is not in senice beyond I hour per  ;

TS 3.13.9.B, CORE ALTERATIONS will be suspended. Therefore, this change does not )

involve a significant reduction in a margin ofsafety.

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l ATTACilM ENT D l ZION NUCl. EAR GENERATING STATION '

ENVIRONMENTAL ASSESSMENT STATEMENT FOR PROPOSED CII ANGES TO FACILITY OPERATING LICENSES j DPR-39 AND DPR-48 )

APPENDIX A TECilNICAL SPECIFICATIONS l RIIR REQUIREMENTS DilRING CORE ALTERATION OPERATIONS I

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.o The proposed changes of this license amendment request have been evaluated against the criteria for s

and identification oflicensing and regulatory actions requiring environmen al assessment in accordance I

with 10 CFR 51.21. It has been detennined that the proposed changes meet the criteria for categorical exclusion as provided for under 10 CFR 51.22(c)(9). The following is a discussion of how the proposed changes meet the criteria for categorical exclusion.

, 10 CFR 51.22(c)(9): Although the proposed changes involve changes to requirements with respect to

the installation or use offacility components or to an inspection or Surveillance Requirements

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, (i) The proposed changes involve no significant hazards considerations (refer to J Attachment C of this license amendment request);

(ii) There is no significant change in the types or a significant increase in the amounts of l

any effluent that may be released offsite, since the proposed changes do not affect the )

generation of any radioactive efHuent nor do they affect any of the permitted release i paths; and

. (iii) There is no significant increase in individual or cumulative occupational radiation

exposure. The actions proposed in this request for an amendment do not significantly affect plant radiation levels, and therefore do not significantly affect dose rates and occupational exposure.

Accordingly, the proposed changes meet the eligibility criteria for categorical exclusion set forth in 10 l

CFR 51.22(c)(9). Based on the aforementioned and pursuant to 10 CFR 51.22(b), no environmental i assessment or environmental impact statement need be prepared in connection with issuance of a license amendment incorporating the proposed change.

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