Text

TS Revision to Allow Fuel Movement with Refueling Interlock Inoperable
	ML032480656
Person / Time
Site:	Hatch
Issue date:	09/02/2003
From:	Sumner H; Southern Nuclear Operating Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	NL-03-1563
	Download: ML032480656 (47)
	v • d • e

H.L Sumner, Jr. Southern Nuclear Vice President Operating Company, Inc.

Hatch Project Post Office Box 1295 Birmingham. Alabama 35201 Tel 205.992.7279 SOUTHERNAML September 2, 2003 COMPANY Energy to ServeYour World' Docket Nos.: 50-321 NL-03-1563 50-366 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Edwin L. Hatch Nuclear Plant Technical Specifications Revision to Allow Fuel Movement with Refueling Interlocks Inoperable Ladies and Gentlemen:

In accordance with the requirements of 10 CFR 50.90, Southern Nuclear Operating Company (SNC) proposes to revise the Plant Hatch Units I and 2 Technical Specifications (TS) to Operating License DPF-57 and NPF-5, respectively.

The proposed revision is to the Refueling Limiting Condition for Operation, section 3.9.1.

Briefly, alternate actions are proposed which will allow in-vessel fuel movements with the refueling interlocks inoperable. The new actions will require that all control rods be fully inserted and that a control rod withdrawal block remain effective until the in-vessel fuel movements are terminated, or until the refuel interlocks are once again operable.

The proposed change is consistent with Technical Specification Task Force (TSTF) change traveler 225, revision 2. provides a description and justification of the proposed change. Enclosure 2 contains the 10 CFR 50.92 evaluation and the justification for the categorical exclusion from performing an environmental assessment. Enclosure 3 provides the marked-up TS and Bases pages. Enclosure 4 provides the clean typed TS and Bases pages.

In accordance with the requirements of 10 CFR 50.91, a copy of this letter and all applicable enclosures will be sent to the designated state official of the Environmental Protection Division of the Georgia Department of Natural Resources.

40cci

U. S. Nuclear Regulatory Commission NL-03-1563 Page 2 Mr. H. L. Sumner states he is a Vice President of the Southern Nuclear Operating Company and is authorized to execute this oath on behalf of Southern Nuclear Operating Company and to the best of his knowledge and belief, the statements set forth in this letter are true.

This letter contains no NRC commitments. If you have any questions, please advise.

Sincerely, H. L. Sumner, Jr.

. '. Sw~,r~o and subscribedbefore me this &dday 0 fS9 ktfl 4.r .2003.

_-__ '~

ByPublic L i .M~c~j~ission on.. expires: ao0 7 HLS/OCV/sdl

Enclosures:

1. Description and Justification for Change

2. No Significant Hazards Evaluation

3. Marked-up Technical Specifications and Bases Pages

4. Published Technical Specifications and Bases Pages cc: Southern Nuclear Operating Company Mr. J. D. Woodard, Executive Vice President Mr. G. R. Frederick, General Manager - Plant Hatch Document Services RTYPE: CHAO2.004 U. S. Nuclear Regulatory Commission Mr. L. A. Reyes, Regional Administrator Mr. S. D. Bloom, NRR Project Manager - Hatch Mr. D. S. Simpkins, Senior Resident Inspector - Hatch State of Georgia Mr. L. C. Barret, Commissioner - Department of Natural Resources

Enclosure 1 Edwin I. Hatch Nuclear Plant Technical Specifications Revision to Allow Fuel Movement with Inoperable Refueling Interlocks Description and Justification for Change This is a proposed change to the Plant Hatch Units 1 and 2 Technical Specifications section 3.9.1 concerning the refueling interlocks. Specifically, an alternate Required Action is being proposed if the refueling interlocks become inoperable. This new ACTION will safely permit continued fuel movement provided:

a) a continuous rod withdrawal block is inserted to replace the conditional rod block provided by the interlocks and, b) all the control rods in the core are verified to be fully inserted.

Additionally, the frequency of performing the Channel Functional Test on each of the required refueling equipment is being changed from 7 days to 31 days.

These changes are consistent with industry/TSTF-225, Revision 2, and are already allowed by the BWR/6 Standard Technical Specifications LCO 3.9.1.

The refueling interlocks act as backup to procedures to prevent inadvertent criticalities during in-vessel fuel movements. The interlocks circuitry senses the conditions of the refueling equipment and the withdrawal of the control rods. Depending on these conditions, the interlocks actuate to prevent the operation of the refueling equipment or the control rods.

There are three types of refueling interlocks:

1) those that prevent control rod motion by causing rod blocks,

2) those that prevent the refueling platform from traveling over the core and,

3) those that prevent hoist operation.

Briefly, the refueling interlocks will not allow fuel to be moved in or near the core unless all control rods are fully inserted, and they prevent the operation of loaded refueling equipment over the core when any control rod is withdrawn. The interlocks also prevent the withdrawal of any control rod when fuel is loaded on refueling equipment and operating over the core.

The refueling interlocks permit fuel movement to proceed without the need to have a control rod block in effect. Accordingly, the Hatch Technical Specifications do not allow refueling to continue if the refueling interlocks are inoperable, even though there is an alternate action (fully insert all control rods and ensure a rod block is in effect) which will provide the same level of safety.

El-l Description and Justification for Change Therefore, the proposed change adds required actions to provide an alternate method for ensuring the reactor remains shutdown during the refueling process if the refueling interlocks become inoperable.

The proposed ACTIONs would function as follows:

LCO ACTION 3.9.1 A.1 will require the suspension of fuel movements if a refueling interlock is inoperable. This remains unchanged.

Proposed ACTION A.2.1 will state that, as an alternative to the suspension of fuel movements, a control rod block must be placed in effect.

Proposed ACTION A.2.2 will require verification that all control rods are indeed fully inserted. This is in addition to the requirements to periodically verify the position of the control rods already in effect via Surveillance Requirement (SR) 3.9.3.1.

ACTIONs A.2.1 and A.2.2 will therefore also ensure that unacceptable operations are blocked (e.g., loading fuel into a cell with a withdrawn control rod).

The change allows Plant Hatch to continue to safely perform fuel movements in the vessel should the interlocks become inoperable for any reason, whether it be due to an administrative declaration (because the surveillance is overdue) or due to a hardware problem.

As pointed out in TSTF-225, these Required Actions have previously been approved for the Perry Nuclear Plant. A similar TS has also been granted to the Pilgrim station.

The proposed change also changes the frequency of SR 3.9.1.1, Channel Functional Test on the refueling interlocks, from 7 days to 31 days.

This change will permit Plant Hatch to not administratively declare the refueling interlocks inoperable after 7 days, when they are still functional. The SR currently requires the channel functional test to be performed every 7 days during in-vessel fuel movement using equipment associated with the refueling interlocks. This includes testing the all-rods-in, refuel platform position, and the refuel grapple full-up position interlocks, among others. To meet the SR, the test must be performed within the 7 day period prior to in-vessel fuel movements and every 7 days thereafter as long as fuel movement continues.

The changes made to the Required Actions will permit a complete offload, shuffle, or fuel load, without the need to halt refueling activities solely for the performance of these tests. Without the relaxation in the SR frequency, however, the operator would be required to administratively declare the interlocks inoperable (even with the additional Required Actions) due to the SR being overdue, although the interlocks would still be capable of performing their safety function.

El-2

I 1J Enclosure 1 Description and Justification for Change A refueling period may last longer than 7 days. Performance of the surveillance during fuel movement causes a disruption in the continuity of fuel movement operations. Thus, this change reduces the risk associated with the halting and recommencing of fuel movement activities by eliminating the discontinuity.

This reduction in surveillance frequency is consistent with the Bases for SR 3.9.1.1 which states that the SR frequency was based on engineering judgment and was considered adequate in view of other indications of refueling status and the associated input status available to the operators. This Bases justification is valid for a 31 day frequency as well.

Furthermore, the proposed SR frequency is consistent with the channel functional test frequency for the control rod blocks in mode 1 as provided in LCO 3.3.2.1, (184 days for the Rod Block Monitor and 92 days for the Rod Worth Minimizer).

E1-3

Enclosure 2 Edwin I. Hatch Nuclear Plant Technical Specifications Revision to Allow Fuel Movement with Inoperable Refueling Interlocks No Significant Hazards Evaluation and Environmental Assessment Proposed Change An alternate Required Action is being provided in LCO 3.9.1 if the refueling interlocks become inoperable. Currently, in-vessel fuel movement must be suspended if the refueling interlocks are inoperable. This ACTION is being preserved, but an alternative action is proposed which will allow continued fuel movement provided:

a) that a continuous rod block is inserted to replace the conditional rod block provided by the interlocks, and b) that all control rods in the core are verified to be fully inserted.

Additionally, the frequency of performing a functional test on each of the required refueling interlocks is reduced from 7 to 31 days.

10 CFR 50.92 Evaluation In 10 CFR 50.92(c), the Nuclear Regulatory Commission (NRC) provides the following standards to be followed in determining the existence of a significant hazards consideration:

....a proposed amendment to an operating license for a facility licensed under 50.21(b) or 50.22, or for a testing facility involves no significant hazards consideration, if operation of the facility in accordance with the proposed amendment would not: (1) Involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) Create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) Involve a significant reduction in the margin of safety.

Southern Nuclear Operating Company (SNC) has reviewed the proposed amendment request and determined that its adoption does not involve a significant hazards consideration based upon the following discussion:

1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?

The proposed change provides additional actions for an inoperable required refueling equipment interlock and reduces the frequency for performing the channel functional test from 7 to 31 days. The actions taken when a refueling interlock is inoperable are not initiators to any previously evaluated accident. Also, the time between Surveillances is not an initiator to any accident previously evaluated. Consequently, the probability of occurrence of a previously evaluated event is not increased.

E2-1

I. I Enclosure 2 No Significant Hazards Evaluation and Environmental Assessment If a refueling accident were to occur while taking the new proposed ACTIONs, the consequences of the event would not be increased since all control rods will be fully inserted. The reduced frequency of the surveillance does not alter the requirement for the equipment to be OPERABLE. As a result, the consequences of any accident previously evaluated are not significantly altered. Therefore, this proposed change does not involve a significant increase in the probability or the consequences of an accident previously evaluated.

2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?

The proposed change provides additional actions for inoperable refueling interlocks and reduces the frequency for performing the Channel Functional Test from 7 to 31 days.

The proposed change does not involve a physical alteration of the plant (no new or different type of equipment is being installed). Also, no new modes of operation are being introduced. Therefore, the change does not create the possibility of a new or different kind of accident from any previously evaluated.

3. Does the proposed change involve a significant reduction in the margin of safety?

The proposed change provides additional actions for an inoperable required refueling equipment interlock and reduces the frequency for performing the Channel Functional Test from 7 to 31 days. The proposed actions provide a level of safety equivalent to the existing actions.

The reduced frequency does not affect the requirement that the equipment be operable.

Furthermore, it is likely that operators would notice a failure of the interlocks via the indications available to them.

For the above reasons, the change does not involve a significant reduction in the margin of safety.

Environmental Assessment 10 CFR 51.22(c) (9) provides criteria for the categorical exclusion from performing an environmental assessment. A proposed amendment to an operating license for a facility requires no environmental assessment if operation of the facility in accordance with the proposed license amendment will not:

1. Involve a significant hazards consideration;

2. Result in a significant change in the types, or a significant increase in the amounts of any effluents that may be released off-site, or, E2-2 No Significant Hazards Evaluation and Environmental Assessment

3. Result in a significant increase in individual or cumulative occupational radiation exposure.

Southern Nuclear has evaluated the proposed changes and determined that the changes do not involve (1) a significant hazards consideration, (2) a significant change in the types or significant increase in the amounts of any effluents that may be released off-site, or (3) a significant increase in the individual or cumulative occupational exposure. Accordingly, the proposed changes meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c) (9), and an environmental assessment of the proposed changes is not required.

E2-3

Enclosure 3 Edwin L Hatch Nuclear Plant Technical Specifications Revision to Allow Fuel Movement with Inoperable Refueling Interlocks Marked-up Technical Specifications and Bases pages

Refueling Equipment Interlocks 3.9.1 3.9 REFUELING OPERATIONS 3.9.1 Refueling Equipment Interlocks LCO 3.9.1 The refueling equipment interlocks shall be OPERABLE.

APPLICABILITY: During in-vessel fuel movement with equipment associated with the interlocks.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Suspend in-vessel fuel Immediately refueling equipment movement with Interlocks inoperable. equipment associated with the inoperable interlock(s).

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.1.1 Perform CHANNEL FUNCTIONAL TEST on each Ydays of the following required refueling equipment 31 interlock Inputs:

a. All-rods-in,

b. Refuel platform position,

c. Refuel platform fuel grapple, fuel loaded,

d. Refuel platform fuel grapple full-up position,

e. Refuel platform frame-mounted hoist, fuel loaded,

f. Refuel platform trolley-mounted hoist, fuel loaded, and

9. Service platform hoist, fuel loaded.

mnmn o 9 HAC_ NT_391 HATCH UNIT I 3.9-1 Amendment No. 195

Refueling Equipment Interlocks 3.9.1 3.9 REFUELING OPERATIONS 3.9.1 Refueling Equipment Interlocks LCO 3.9.1 The refueling equipment interlocks shall be OPERABLE.

APPLICABILITY: During in-vessel fuel movement with equipment associated with the interlocks.

ACTIONS CONDITION REQUiRED ACTION COMPLETION TIME A. One or more required A.1 Suspend in-vessel fuel Immediately refueling equipment movement with interlocks Inoperable. equipment associated with the inoperable interlock(s).

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.1.1 Perform CHANNEL FUNCTIONAL TEST on each /days of the following required refueling equipment 31 interlock Inputs:

a. All-rods-in,

b. Refuel platform position,

c. Refuel platform fuel grapple, fuel loaded,

d. Refuel platform fuel grapple full-up position,

e. Refuel platform frame-mounted hoist, fuel loaded,

f. Refuel platform trolley-mounted hoist, fuel loaded, and

g. Service platform hoist, fuel loaded.

HATCH UNIT 2 3.9-1 Amendment No. 135

.z OR A.2.1 Insert a control rod Immediately withdrawal block.

AND A.2.2 Verify all control rods Immediately are fully inserted.

1.

i i

I I

ii

Refueling Equipment Interlocks B 3.9.1 BASES (continued)

APPLICABILITY In MODE 5, a prompt reactivity excursion could cause fuel damage and subsequent release of radioactive material to the environment.

The refueling equipment interlocks protect against prompt reactivity excursions during MODE 5. The interlocks are required to be OPERABLE during in-vessel fuel movement with refueling equipment associated with the interlocks.

In MODES 1, 2, 3, and 4, the reactor pressure vessel head is on, and CORE ALTERATIONS are not possible. Therefore, the refueling interlocks are not required to be OPERABLE in these MODES.

ACTIONS M n n,~_

~~~~a A. a_ .

With one or more of the required refueling equipment interlocks INSR v t 1r3t inoperable, the unit must be placed in a condition in which the LVS~O does not apply,,Iln-vessel fuel movement with the affected refueling equipment must be immediately suspended. This action ensures that operations are not performed with equipment that would potentially not be blocked from unacceptable operations (e.g., loading fuel into a cell with a control rod withdrawn). Suspension of in-vessel fuel movement shall not preclude completion of movement of a component to a safe position.

~

SURVEILLANCE SR 9.9.1.1 REQUIREMENTS Performance of a CHANNEL FUNCTIONAL TEST demonstrates each required refueling equipment Interlock will function properly when a simulated or actual signal indicative of a required condition is injected into the logic. The CHANNEL FUNCTIONAL TEST may be performed by any series of sequential, overlapping, or total channel steps so that the entire channel is tested.

31( 7 e day Frequency is based on engineering judgment and is considered adequate in view of other indications of refueling interlocks and their associated input status that are available to unit operations personnel.

(continued)

HATCH UNIT 1 B 3.9-3 REVISION 0

I1 A Refueling Equipment Interlocks B 3.9.1 BASES (continued)

APPLICABILITY In MODE 5, a prompt reactivity excursion could cause fuel damage and subsequent release of radioactive material to the environment.

The refueling equipment interlocks protect against prompt reactivity excursions during MODE 5. The interlocks are required to be OPERABLE during in-vessel fuel movement with refueling equipment associated with the interlocks.

In MODES 1, 2, 3, and 4, the reactor pressure vessel head is on, and CORE ALTERATIONS are not possible. Therefore, the refueling interlocks are not required to be OPERABLE in these MODES.

ACTIONS A.1L 9 3..L With one or more of the required refueling equipment interlocks dd minoperable, the unit must be placed Ina condition in which the

~NSEI.T 81 LCO does not apply,, In-vessel fuel movement with the affected refueling equipment must be immediately suspended. This action ensures that operations are not performed with equipment that would potentially not be blocked from unacceptable operations (e.g., loading fuel into a cell with a control rod withdrawn). Suspension of in-vessel fuel movement shall not preclude completion of movement of a z .4d A component to a safe position.

SURVEILLANCE SR 3.9.1.1 REQUIREMENTS Performance of a CHANNEL FUNCTIONAL TEST demonstrates each required refueling equipment interlock will function properly when a simulated or actual signal indicative of a required condition Is injected into the logic. The CHANNEL FUNCTIONAL TEST may be performed by any series of sequential, overlapping, or total channel steps so that the entire channel is tested.

31 The/day Frequency is based on engineering judgment and is considered adequate in view of other indications of refueling interlocks and their associated input status that are available to unit operations personnel.

(continued)

HATCH UNIT 2 B 3.9-3 REVISION 0

ss ^

INSERT B1

...(Required Action A. l)or the interlocks are not needed (Required Action A.2).

INSERT B2 Alternatively, Required Actions A.2.1 and A.2.2 will permit continued fuel movement with the interlocks inoperable if a control rod withdrawal block is inserted, and all control rods are subsequently verified to be fully inserted. Required Action A.2.1 (rod block) ensures no control rods can be withdrawn. The withdrawal block utilized must ensure that if rod withdrawal is requested, the rod will not respond (i.e., it will remain inserted).

Required Action A.2.2 is performed after placing the rod withdrawal in effect, and provides a verification that all control rods are fully inserted. This verification that all control rods are fully inserted is in addition to the periodic verifications required by SR 3.9.3.1. Like Required Action A.1, Required Actions A.2.1 and A.2.2 ensure unacceptable operations are blocked (e.g. loading fuel into a cell with a control rod withdrawn.

The alternate ACTIONS, as given by A.2.1 and A.2.2, provide a level of protection which is, at least, equivalent to the refueling interlocks.

One use for the A.2 Required Actions is to permit performance of SR 3.9.1.1 once, prior to fuel movement, without the need for subsequent performance if the fuel movement period extends longer than the 31 day frequency of the SR. This permits continued fuel movement under the protection of the continuous rod block inserted by the Required Actions.

Enclosure 4 Edwin L Hatch Nuclear Plant Technical Specifications Revision to -Allow Fuel Movement with Inoperable Refueling Interlocks Clean Typed Technical Specifications and Bases pages

TABLE OF CONTENTS (continued) 3.6 CONTAINMENT SYSTEMS (continued) 3.6.1.6 Low-Low Set (LLS) Valves .3.6-15 3.6.1.7 Reactor Building-to-Suppression Chamber Vacuum Breakers .3.6-17 3.6.1.8 Suppression Chamber-to-Drywell Vacuum Breakers .3.6-19 3.6.2.1 Suppression Pool Average Temperature .3.6-21 3.6.2.2 Suppression Pool Water Level .................... 3.6-24 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling .......................... 3.6-25 3.6.2.4 Residual Heat Removal (RHR) Suppression Pool Spray ................. ........... 3.6-27 3.6.3.1 Containment Atmosphere Dilution (CAD) System ....................................... 3.6-29 3.6.3.2 Primary Containment Oxygen Concentration ............................................. 3.6-31 3.6.4.1 Secondary Containment ............................................... 3.6-32 3.6.4.2 Secondary Containment Isolation Valves (SCIVs) ...................................... 3.6-35 3.6.4.3 Standby Gas Treatment (SGT) System.............................................. 3.6-38 3.7 PLANTSYSTEMS ............................................... 3.7-1 3.7.1 Residual Heat Removal Service Water (RHRSW) System .......................... 3.7-1 3.7.2 Plant Service Water (PSW) System and Ultimate Heat Sink (UHS) ......... ... 3.7-3 3.7.3 Diesel Generator (DG) 1B Standby Service Water (SSW) System.............. 3.7-6 3.7.4 Main Control Room Environmental Control (MCREC) System .................... 3.7-8 3.7.5 Control Room Air Conditioning (AC) System .............................................. 3.7-12 3.7.6 Main Condenser Offgas . ............................................. 3.7-16 3.7.7 Main Turbine Bypass System . .............................................. 3.7-18 3.7.8 Spent Fuel Storage Pool Water Level .............................. ................ 3.7-19 3.8 ELECTRICAL POWER SYSTEMS .............................................. 3.8-1 3.8.1 AC Sources - Operating .............................................. 3.8-1 3.8.2 AC Sources - Shutdown .............................................. 3.8-20 3.8.3 Diesel Fuel Oil and Transfer, Lube Oil, and Starting Air .............................. 3.8-23 3.8.4 DC Sources - Operating .............................................. 3.8-26 3.8.5 DC Sources - Shutdown .............................................. 3.8-31 3.8.6 Battery Cell Parameters .............................................. 3.8-33 3.8.7 Distribution Systems - Operating .............................................. 3.8-36 3.8.8 Distribution Systems - Shutdown .................. .....................; . .... 3.8-39 3.9 REFUELING OPERATIONS .............................................. 3.9-1 3.9.1 Refueling Equipment Interlocks ............................................... 3.9-1 3.9.2 Refuel Position One-Rod-Out Interlock .............................................. 3.9-3 3.9.3 Control Rod Position .............................................. 3.9-4 3.9.4 Control Rod Position Indication .............................................. 3.9-5 (continued)

HATCH UNIT 1 Hii Amendment No.

J TABLE OF CONTENTS (continued) 3.9 REFUELING OPERATIONS (continued) 3.9.5 Control Rod OPERABILITY - Refueling .................................... 3.9-7 3.9.6 Reactor Pressure Vessel (RPV) Water Level .................................... 3.9-8 3.9.7 Residual Heat Removal (RHR) - High Water Level .................................... 3.9-9 3.9.8 Residual Heat Removal (RHR) - Low Water Level .................................... 3.9-11 3.10 SPECIAL OPERATIONS .................................... 3.10-1 3.10.1 Inservice Leak and Hydrostatic Testing Operation .................................... 3.10-1 3.10.2 Reactor Mode Switch Interlock Testing ............. ....................... 3.10-3 3.10.3 Single Control Rod Withdrawal - Hot Shutdown .................................... 3.10-5 3.10.4 Single Control Rod Withdrawal - Cold Shutdown ..................................... 3.10-8 3.10.5 Single Control Rod Drive (CRD) Removal - Refueling ................................. 3.10-11 3.10.6 Multiple Control Rod Withdrawal - Refueling .................................... 3.10-13 3.10.7 Control Rod Testing - Operating .................................... 3.10-15 3.10.8 SHUTDOWN MARGIN (SDM) Test - Refueling .................................... 3.10-17 4.0 DESIGN FEATURES .................................... 4.0-1 4.1 Site .................................... 4.01 4.2 Reactor Core .................................... 4.0-1 4.3 Fuel Storage .................................... 4.0-2 5.0 ADMINISTRATIVE CONTROLS ..................................... 5.0-1 5.1 Responsibility.................................... 5.0-1 5.2 Organization .................................... 5.0-2 5.3 Unit Staff Qualifications .................................... 5.0-5 5.4 Procedures .................................... 5.0-6 5.5 Programs and Manuals .................................... 5.0-7 5.6 Reporting Requirements .................................... 5.0-18 5.7 High Radiation Area .................................... 5.0-21 (continued)

HATCH UNIT I IV Amendment No.

Refueling Equipment Interlocks 3.9.1 3.9 REFUELING OPERATIONS 3.9.1 Refueling Equipment Interlocks LCO 3.9.1 The refueling equipment interlocks shall be OPERABLE.

APPLICABILITY: During in-vessel fuel movement with equipment associated with the interlocks.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Suspend In-vessel fuel Immediately refueling equipment movement with interlocks inoperable. equipment associated with the inoperable interlock(s).

OR A.2.1 Insert a control rod Immediately withdrawal block.

AND A.2.2 Verify all control rods are Immediately fully inserted.

HATCH UNIT I 3.9-1 Amendment No.

Refueling Equipment Interlocks 3.9.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.1.1 Perform CHANNEL FUNCTIONAL TEST on each 31 days I of the following required refueling equipment Interlock Inputs:

a. All-rods-in,

b. Refuel platform position,

c. Refuel platform fuel grapple, fuel loaded,

d. Refuel platform fuel grapple full-up position,

e. Refuel platform frame-mounted hoist, fuel loaded,

f. Refuel platform trolley-mounted hoist, fuel loaded, and

9. Service platform hoist, fuel loaded.

HATCH UNIT 1 3.9-2 Amendment No.

.1 Refuel Position One-Rod-Out Interlock 3.9.2 3.9 REFUELING OPERATIONS 3.9.2 Refuel Position One-Rod-Out Interlock LCO 3.9.2 ,The refuel position one-rod-out interlock shall be OPERABLE.

APPLICABILITY: MODE 5 with the reactor mode switch in the refuel position and any control rod withdrawn.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Refuel position one-rod-out A.1 Suspend control rod Immediately Interlock inoperable. withdrawal.

AND A.2 Initiate action to fully Immediately insert all Insertable control rods In core cells containing one or more fuel assemblies.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.2.1 Verify reactor mode switch locked in refuel 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months position.

SR 3.9.2.2 ----- ----------- NOTE--------

Not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after any control rod is withdrawn.

Perform CHANNEL FUNCTIONAL TEST. 7 days HATCH UNIT 1 3.9-3 Amendment No. I

Control Rod Position 3.9.3 3.9 REFUELING OPERATIONS 3.9.3 Control Rod Position LCO 3.9.3 All control rods shall be fully inserted.

APPLICABILITY: When loading fuel assemblies into the core.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more control rods A.1 Suspend loading fuel Immediately not fully inserted. assemblies into the core.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.3.1 Verify all control rods are fully inserted. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months HATCH UNIT 1 3.9-4 Amendment No. I

I .1 Control Rod Position Indication 3.9.4 3.9 REFUELING OPERATIONS 3.9.4 Control Rod Position Indication LCO 3.9.4 The control rod full-in position indication channel for each control rod shall be OPERABLE.

APPLICABILITY: MODE 5.

ACTIONS

- ----- ------------------- NOTE-E ---------------- ----------------------

Separate Condition entry is allowed for each required channel.

._ _ ~ -- - --- --- - -_-- - - _ _--- - -----

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1.1 Suspend In-vessel fuel Immediately control rod position movement.

Indication channels Inoperable. AND A.1.2 Suspend control rod Immediately withdrawal.

AND A.1.3 Initiate action to fully Immediately insert all Insertable control rods In core cells containing one or more fuel assemblies.

OR A.2.1 Initiate action to fully Immediately Insert the control rod associated with the inoperable position Indicator.

AND (continued)

HATCH UNIT 1 3.9-5 Amendment No.

Control Rod Position Indication 3.9.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.2 Initiate action to disarm Immediately the control rod drive associated with the fully inserted control rod.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.4.1 Verify the required channel has no full-in indication Each time the on each control rod that Is not full-in. control rod is withdrawn from the full-in position HATCH UNIT 1 3.9-6 Amendment No. I

Control Rod OPERABILITY - Refueling 3.9.5 3.9 REFUELING OPERATIONS 3.9.5 Control Rod OPERABILITY - Refueling LCO 3.9.5 Each withdrawn control rod shall be OPERABLE.

APPLICABILITY: MODE 5.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more withdrawn A.1 Initiate action to fully Immediately control rods Inoperable. insert inoperable withdrawn control rods.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.5.1 -o-- -----..- NOTE---------------------

Not required to be performed until 7 days after the control rod Is withdrawn.

Insert each withdrawn control rod at least one 7 days notch.

SR 3.9.5.2 Verify each withdrawn control rod scram 7 days accumulator pressure is 2 940 psig.

HATCH UNIT 1 3.9-7 Amendment No. I

RPV Water Level 3.9.6 3.9 REFUELING OPERATIONS 3.9.6 Reactor Pressure Vessel (RPV) Water Level LCO 3.9.6 RPV water level shall be 2 23 ft above the top of the Irradiated fuel assemblies seated within the RPV.

APPUCABILITY: During movement of irradiated fuel assemblies within the RPV, During movement of new fuel assemblies or handling of control rods within the RPV, when irradiated fuel assemblies are seated within the RPV.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RPV water level not within A.1 Suspend movement of Immediately limit. fuel assemblies and handling of control rods within the RPV.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.6.1 Verify RPV water level Is 2 23 ft above the top of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months the irradiated fuel assemblies seated within the RPV.

HATCH UNIT 1 3.9-8 Amendment No. I

RHR - High Water Level 3.9.7 3.9 REFUELING OPERATIONS 3.9.7 Residual Heat Removal (RHR) - High Water Level LCO 3.9.7 One RHR shutdown cooling subsystem shall be OPERABLE and in operation.

___------------Nj a we.~I I- _-- _-- .--_-- _-- _-- _-- _-- .-..- __- __- __- __- __- __- __- _

The required RHR shutdown cooling subsystem 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.

A.. -

APPLICABILITY: MODE 5 with irradiated fuel in the reactor pressure vessel (RPV) and the water level k 22 ft 1/8 inches above the top of the RPV flange.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Required RHR shutdown A.1 Verify an alternate 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months cooling subsystem method of decay heat inoperable. removal is available. AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter B. Required Action and B.1 Suspend loading Immediately associated Completion irradiated fuel Time of Condition A not assemblies into the met. RPV.

AND B.2 Initiate action to restore Immediately secondary containment to OPERABLE status.

AND (continued)

HATCH UNIT 1 3.9-9 Amendment No. I

RHR - High Water Level 3.9.7 ACTIONS :

CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.3 Initiate action to restore Immediately required standby gas treatment subsystem(s) to OPERABLE status.

AND B.4 Initiate action to restore Immediately isolation capability in each required secondary containment penetration flow path not Isolated.

C. No RHR shutdown cooling C.1 Verify reactor coolant 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery subsystem in operation. circulation by an of no reactor coolant alternate method. circulation AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND C.2 Monitor reactor coolant Once per hour temperature.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.7.1 Verify one RHR shutdown cooling subsystem is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months operating.

HATCH UNIT I 3.9-10 Amendment No.

RHR - Low Water Level 3.9.8 3.9 REFUELING OPERATIONS 3.9.8 Residual Heat Removal (RHR) - Low Water Level LCO 3.9.8 Two RHR shutdown cooling subsystems shall be OPERABLE, and one RHR shutdown cooling subsystem shall be in operation.

i------

i-~~~~~~ - .. IILGNI t~ ~~~~~~~~

The required operating shutdown cooling subsystem 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.

APPLICABILITY: MODE 5 with irradiated fuel in the reactor pressure vessel (RPV) and the water level < 22 ft 1/8 inches above the top of the RPV flange.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or two required RHR A.1 Verify an alternate 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months shutdown cooling method of decay heat subsystems inoperable. removal is available for AND each Inoperable required RHR shutdown Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months cooling subsystem. thereafter B. Required Action and B.1 Initiate action to restore Immediately associated Completion secondary containment Time of Condition A not to OPERABLE status.

met.

AND B.2 Initiate action to restore Immediately required standby gas treatment subsystem(s) to OPERABLE status.

AND (continued)

HATCH UNIT I 3.9-11 Amendment No. I

RHR - Low Water Level 3.9.8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.3 Initiate action to restore Immediately isolation capability in each required secondary containment penetration flow path not isolated.

C. No RHR shutdown cooling C.1 Verify reactor coolant 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery subsystem in operation. circulation by an of no reactor coolant alternate method. circulation AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND C.2 Monitor reactor coolant Once per hour temperature.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.8.1 Verify one RHR shutdown cooling subsystem is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months operating.

HATCH UNIT 1 3.9-12 Amendment No.

I

TABLE OF CONTENTS 3.8 ELECTRICAL POWER SYSTEMS (continued) 3.8.6 Battery Cell Parameters .................................. 3.8-33 3.8.7 Distribution Systems - Operating .................................. 3.8-36 3.8.8 Distribution Systems - Shutdown .................................. 3.8-39 3.9 REFUELING OPERATIONS .................................. 3.9-1 3.9.1 Refueling Equipment Interlocks .................................. 3.9-1 3.9.2 Refuel Position One-Rod-Out Interlock....................................................... 93.93 3.9.3 Control Rod Position .................................. 3.9-4 3.9.4 Control Rod Position Indication .................................. 3.9-5 3.9.5 Control Rod OPERABILITY - Refueling ............ ...................... 3.9-7 3.9.6 Reactor Pressure Vessel (RPV) Water Level .................................. 3.9-8 3.9.7 Residual Heat Removal (RHR) - High Water Level .................................. 3.9-9 3.9.8 Residual Heat Removal (RHR) - Low Water Level .................................. 3.9-11 3.10 SPECIAL OPERATIONS .................................. 3.10-1 3.10.1 Inservice Leak and Hydrostatic Testing Operation ................................... 3.10-1 3.10.2 Reactor Mode Switch Interlock Testing .................................. 3.10-3 3.10.3 Single Control Rod Withdrawal - Hot Shutdown .............................. .... 3.10-5 3.10.4 Single Control Rod Withdrawal - Cold Shutdown .................................. 3.10-8 3.10.5 Single Control Rod Drive (CRD)

Removal - Refueling ................................ 3.10-11 3.10.6 Multiple Control Rod Withdrawal - Refueling ................................ 3.10-13 3.10.7 Control Rod Testing - Operating ................................ 3.10-15 3.10.8 SHUTDOWN MARGIN (SDM) Test - Refueling ....................... ......... 3.10-17 4.0 DESIGN FEATURES ................................ 4.0-1 4.1 Site ................................ 4.0-1 4.2 Reactor Core ................................ 4.0-1 4.3 Fuel Storage ................................ 4.0-2 (continued)

HATCH UNIT 2 IV Amendment No.

Refueling Equipment Interlocks 3.9.1 3.9 REFUELING OPERATIONS 3.9.1 Refueling Equipment Interlocks LCO 3.9.1 The refueling equipment interlocks shall be OPERABLE.

APPLICABILITY: During in-vessel fuel movement with equipment associated with the interlocks.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Suspend in-vessel fuel Immediately refueling equipment movement with interlocks inoperable. equipment associated with the inoperable interlock(s).

OR A.2.1 Insert a control rod Immediately withdrawal block.

AND A.2.2 Verify all control rods are Immediately fully inserted.

HATCH UNIT 2 3.9-1 Amendment No.

- Refueling Equipment Interlocks 3.9.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

.9 SR 3.9.1.1 Perform CHANNEL FUNCTIONAL TEST on each 31 days I of the following required refueling equipment interlock inputs:

a. All-rods-in,

b. Refuel platform position,

c. Refuel platform fuel grapple, fuel loaded,

d. Refuel platform fuel grapple full-up position,

e. Refuel platform frame-mounted hoist, fuel loaded,

f. Refuel platform trolley-mounted hoist, fuel loaded, and

g. Service platform hoist, fuel loaded.

HATCH UNIT 2 3.9-2 Amendment No.

Refuel Position One-Rod-Out Interlock 3.9.2 3.9 REFUELING OPERATIONS 3.9.2 Refuel Position One-Rod-Out Interlock LCO 3.9.2 The refuel position one-rod-out interlock shall be OPERABLE.

APPLICABILITY: MODE 5 with the reactor mode switch in the refuel position and any control rod withdrawn.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Refuel position one-rod-out A.1 Suspend control rod Immediately Interlock inoperable. withdrawal.

AND A.2 Initiate action to fully Immediately insert all insertable control rods in core cells containing one or more fuel assemblies.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.2.1 Verify reactor mode switch locked in refuel 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months position.

SR 3.9.2.2 - ----------------NOTE-------

Not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after any control rod is withdrawn.

Perform CHANNEL FUNCTIONAL TEST. 7 days HXTCH UNIT 2 3.9-3 Amendment No. I

I ;~

Control Rod Position 3.9.3 3.9 REFUELING OPERATIONS 3.9.3 Control Rod Position LCO 3.9.3 All control rods shall be fully Inserted.

APPLICABILITY: When loading fuel assemblies into the core.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more control rods A.1 Suspend loading fuel Immediately not fully inserted. assemblies into the core.

SURVEILLANCE REQUIREMENTS' SURVEILLANCE FREQUENCY SR 3.9.3.1 Verify all control rods are fully inserted. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months HATCH UNIT 2 3.94 Amendment No. I

I Control Rod Position Indication 3.9.4 3.9 REFUELING OPERATIONS 3.9.4 Control Rod Position Indication LCO 3.9.4 The control rod full-in position Indication channel for each control rod shall be OPERABLE.

APPLICABILITY: MODE 5.

ACTIONS Sep a- e C d-io - e----a- ------is ---------- NOTEq-i h-----e----

Separate Condition entry is allowed for each required channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1.1 Suspend in-vessel fuel Immediately control rod position movement.

indication channels inoperable. AND A.1 .2 Suspend control rod Immediately withdrawal.

AND A.1.3 Initiate action to fully Immediately insert all insertable control rods in core cells containing one or more fuel assemblies.

OR A.2.1 Initiate action to fully Immediately insert the control rod associated with the inoperable position indicator.

AND (continued)

HATCH UNIT 2 3.9-5 Amendment No. I

Control Rod Position Indication 3.9.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.2 Initiate action to disarm Immediately the control rod drive associated with the fully inserted controf rod.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.4.1 Verify the required channel has no full-in indication Each time the on each control rod that is not full-in. control rod is withdrawn from the full-in position HATCH UNIT 2 3.9-6 Amendment No. I

Control Rod OPERABILITY - Refueling 3.9.5 3.9 REFUELING OPERATIONS 3.9.5 Control Rod OPERABILITY - Refueling LCO 3.9.5 Each withdrawn control rod shall be OPERABLE.

APPLICABILITY: MODE 5.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more withdrawn A.1 Initiate action to fully Immediately control rods inoperable. insert inoperable withdrawn control rods.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.5.1 ----- - ---------------NOTE ---------------

Not required to be performed until 7 days after the control rod is withdrawn.

Insert each withdrawn control rod at least one 7 days notch.

SR 3.9.5.2 Verify each withdrawn control rod scram 7 days accumulator pressure is ? 940 psig.

HATCH UNIT 2 3.9-7 Amendment No.

?,

.r .

RPV Water Level 3.9.6 3.9 REFUELING OPERATIONS 3.9.6 Reactor Pressure Vessel (RPV) Water Level LCO 3.9.6 RPV water level shall be 2 23 ft above the top of the irradiated fuel assemblies seated within the RPV.

APPLICABILITY: During movement of irradiated fuel assemblies within the RPV, During movement of new fuel assemblies or handling of control rods within the RPV, when irradiated fuel assemblies are seated within the RPV.

ACTIONS _

CONDITION REQUIRED ACTION COMPLETION TIME A. RPV water level not within A.1 Suspend movement of Immediately limit. fuel assemblies and handling of control rods within the RPV.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.6.1 Verify RPV water level is 2 23 ft above the top of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months the irradiated fuel assemblies seated within the RPV.

HATCH UNIT 2 3.9-8 Amendment No. I

RHR - High Water Level 3.9.7 3.9 REFUELING OPERATIONS 3.9.7 Residual Heat Removal (RHR) - High Water Level LCO 3.9.7 One RHR shutdown cooling subsystem shall be OPERABLE and in operation.

as---------

NUI^TC I A------------------------------------_-

The required RHR shutdown cooling subsystem 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.

APPLICABILITY: MODE 5 with irradiated fuel in the reactor pressure vessel (RPV) and the water level k 22 ft 1/8 inches above the top of the RPV flange.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Required RHR shutdown A.1 Verify an alternate 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months cooling subsystem method of decay heat Inoperable. removal is available. AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter B. Required Action and B.1 Suspend loading Immediately associated Completion irradiated fuel Time of Condition A not assemblies into the met. RPV.

AND B.2 Initiate action to restore Immediately secondary containment to OPERABLE status.

AND (continued)

HATCH UNIT 2 3.9-9 Amendment No. I

RHR - High Water Level 3.9.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.3 Initiate action to restore Immediately required standby gas treatment subsystem(s) to OPERABLE status.

AND B.4 Initiate action to restore Immediately isolation capability in each required secondary containment penetration flow path not Isolated.

C. No RHR shutdown cooling C.1 Verify reactor coolant 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery subsystem In operation. circulation by an of no reactor coolant alternate method. circulation AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND C.2 Monitor reactor coolant Once per hour temperature.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.7.1 Verify one RHR shutdown cooling subsystem is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months operating.

HATCH UNIT 2 3.9-10 Amendment No. l

RHR - Low Water Level 3.9.8 3.9 REFUELING OPERATIONS 3.9.8 Residual Heat Removal (RHR) - Low Water Level LCO 3.9.8 Two RHR shutdown cooling subsystems shall be OPERABLE, and one RHR shutdown cooling subsystem shall be In operation.

-- - ----------------- --------- N c - --- - ----- - --- - ------ - ----

The required operating shutdown cooling subsystem 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.

APPUCABILITY: MODE 5 with irradiated fuel in the reactor pressure vessel (RPV) and the water level < 22 ft 1/8 Inches above the top of the RPV flange.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or two required RHR A.1 Verify an alternate 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months shutdown cooling method of decay heat subsystems inoperable. removal is available for AND each inoperable required RHR shutdown Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months cooling subsystem. thereafter B. Required Action and B.1 Initiate action to restore Immediately associated Completion secondary containment Time of Condition A not to OPERABLE status.

met.

AND B.2 Initiate action to restore Immediately required standby gas treatment subsystem(s) to OPERABLE status.

AND (continued)

HATCH UNIT 2 3.9-11 Amendment No. I

Va te 'b RHR - Low Water Level 3.9.8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.3 Initiate action to restore Immediately Isolation capability in each required secondary containment penetration flow path not isolated.

C. No RHR shutdown cooling C.1 Verify reactor coolant 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery subsystem in operation. circulation by an of no reactor coolant alternate method. circulation AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND C.2 Monitor reactor coolant Once per hour temperature.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.8.1 Verify one RHR shutdown cooling subsystem is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months operating.

HATCH UNIT 2 3.9-12 Amendment No. I

Refueling Equipment Interlocks B 3.9.1 BASES (continued)

APPLICABILITY In MODE 5, a prompt reactivity excursion could cause fuel damage and subsequent release of radioactive material to the environment.

The refueling equipment interlocks protect against prompt reactivity excursions during MODE 5. The interlocks are required to be OPERABLE during in-vessel fuel movement with refueling equipment associated with the interlocks.

In MODES 1, 2, 3, and 4, the reactor pressure vessel head Is on, and CORE ALTERATIONS are not possible. Therefore, the refueling interlocks are not required to be OPERABLE in these MODES.

ACTIONS A.1. A.2.1. and A.2.2 With one or more of the required refueling equipment interlocks inoperable, the unit must be placed In a condition Inwhich the LCO does not apply (Required Action A.1) or the interlocks are not needed (Required Action A.2). In-vessel fuel movement with the affected refueling equipment must be immediately suspended. This action ensures that operations are not performed with equipment that would potentially not be blocked from unacceptable operations (e.g.,

loading fuel into a cell with a control rod withdrawn). Suspension of In-vessel fuel movement shall not preclude completion of movement of a component to a safe position.

Alternatively, Required Actions A.2.1 and A.2.2 will permit continued fuel movement with the Interlocks inoperable If a control rod withdrawal block Is Inserted, and all control rods are subsequently verified to be fully inserted. Required Action A.-2.1 (rod block) ensures no control rods can be withdrawn. The withdrawal block utilized must ensure that if rod withdrawal is requested, the rod will not respond (i.e., it will remain inserted). Required Action A.2.2 is performed after placing the rod withdrawal in effect, and provides verification that all control rods are fully Inserted. This verification that all control rods are fully inserted is in addition to the periodic verifications required by SR 3.9.3.1. Like Required Action A.1, Required Actions A.2.1 and A.2.2 ensure unacceptable operations are blocked (e.g., loading fuel Into a cell with a control rod withdrawn).

The alternate actions as given by A.2.1 and A.2.2 provide a level of protection which is at least equivalent to the refueling interlocks.

One use for the A.2 Required Actions Is to permit performance of SR 3.9.1.1 once, prior to fuel movement, without the need for subsequent performance if the fuel movement period extends longer (continued)

HATCH UNIT 1 B 3.9-3

W Wr /f Refueling Equipment Interlocks B 3.9.1 BASES ACTIONS A.1. A.2.1. and A.2.2 (continued) than the 31 day Frequency of the SR. This permits continued fuel movement under the protection of the continuous rod block inserted by the Required Actions.

SURVEILLANCE SR 3.9.1.1 REQUIREMENTS Performance of a CHANNEL FUNCTIONAL TEST demonstrates each required refueling equipment interlock will function properly when a simulated or actual signal indicative of a required condition is injected into the logic. The CHANNEL FUNCTIONAL TEST may be performed by any series of sequential, overlapping, or total channel steps so that the entire channel is tested.

The 31 day Frequency Is based on engineering judgment and is I considered adequate in view of other Indications of refueling interlocks and their associated Input status that are available to unit operations personnel.

REFERENCES 1. 10 CFR 50, Appendix A, GDC 26.

2. FSAR, Section 7.6.3.

3. FSAR, Section 14.3.3.3.

4. FSAR, Section 14.3.3.4.

5. NRC No.93-102, OFinal Policy Statement on Technical Specification Improvements," July 23, 1993.

HATCH UNIT 1 B 3.9-4

Refueling Equipment Interlocks B 3.9.1 BASES (continued)

APPLICABILITY In MODE 5, a prompt reactivity excursion could cause fuel damage and subsequent release of radioactive material to the environment.

The refueling equipment interlocks protect against prompt reactivity excursions during MODE 5. The Interlocks are required to be OPERABLE during in-vessel fuel movement with refueling equipment associated with the interlocks.

In MODES 1, 2, 3, and 4, the reactor pressure vessel head is on, and CORE ALTERATIONS are not possible. Therefore, the refueling interlocks are not required to be OPERABLE in these MODES.

ACTIONS A.1. A.2.1. and A.2.2 With one or more of the required refueling equipment interlocks inoperable, the unit must be placed in a condition in which the LCO does not apply (Required Action A.1) or the interlocks are not needed (Required Action A.2). In-vessel fuel movement with the affected refueling equipment must be immediately suspended. This action ensures that operations are not performed with equipment that would potentially not be blocked from unacceptable operations (e.g.,

loading fuel into a cell with a control rod withdrawn). Suspension of in-vessel fuel movement shall not preclude completion of movement of a component to a safe position.

Alternatively, Required Actions A.2.1 and A.2.2 will permit continued fuel movement with the interlocks inoperable if a control rod withdrawal block Is inserted, and all control rods are subsequently verified to be fully Inserted. Required Action A.2.1 (rod block) ensures no control rods can be withdrawn. The withdrawal block utilized must ensure that if rod withdrawal is requested, the rod will not respond (i.e., it will remain Inserted). Required Action A.2.2 Is performed after placing the rod withdrawal in effect, and provides verification that all control rods are fully inserted. This verification that all control rods are fully inserted Is in addition to the periodic verifications required by SR 3.9.3.1. Like Required Action A.1, Required Actions A.2.1 and A.2.2 ensure unacceptable operations are blocked (e.g., loading fuel into a cell with a control rod withdrawn).

The alternate actions as given by A.2.1 and A.2.2 provide a level of protection which is at least equivalent to the refueling Interlocks.

One use for the A.2 Required Actions is to permit performance of SR 3.9.1.1 once, prior to fuel movement, without the need for subsequent performance if the fuel movement period extends longer (continued)

HATCH UNIT 2 B 3.9-3

4 %W 4 Refueling Equipment Interlocks B 3.9.1 BASES ACTIONS A.1. A.2.1. and A.2.2 (continued) than the 31 day Frequency of the SR. This permits continued fuel movement under the protection of the continuous rod block inserted by the Required Actions.

SURVEILLANCE SR 3.9.1.1 REQUIREMENTS Performance of a CHANNEL FUNCTIONAL TEST demonstrates each required refueling equipment interlock will function properly when a simulated or actual signal Indicative of a required condition Is injected Into the logic. The CHANNEL FUNCTIONAL TEST may be performed by any series of sequential, overlapping, or total channel steps so that the entire channel is tested.

The 31 day Frequency is based on engineering judgment and is I considered adequate in view of other Indications of refueling interlocks and their associated input status that are available to unit operations personnel.

REFERENCES 1. 10 CFR 50, Appendix A, GDC 26.

2. FSAR, Section 7.6.1.

3. FSAR, Section 15.1.13.

4. FSAR, Section 15.1.14.

5. NRC No.93-102, wFinal Policy Statement on Technical Specification Improvements," July 23, 1993.

HATCH UNIT 2 6 3.9-4

NL-03-1563, TS Revision to Allow Fuel Movement with Refueling Interlock Inoperable

Text

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NL-03-1563, TS Revision to Allow Fuel Movement with Refueling Interlock Inoperable

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