ML18012A581
ML18012A581 | |
Person / Time | |
---|---|
Site: | Harris ![]() |
Issue date: | 03/17/1997 |
From: | CAROLINA POWER & LIGHT CO. |
To: | |
Shared Package | |
ML18012A577 | List: |
References | |
NUDOCS 9703240132 | |
Download: ML18012A581 (32) | |
Text
ENCLOSURE TO SERIAL: HNP-97-056 ENCLOSURE 1 SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT DELETION OF SHUTDOWN REQUIRMENT FROM SELECTED SURVEILLANCES BASIS FOR CHANGE RE UEST
~Back round The Harris Nuclear Plant (HNP) Technical Specifications (TS) establish requirements for the operability of equipment necessary to safely operate the plant. Each Technical Specification requires surveillance activities which establish the operability of the key systems or components necessary to accomplish the Technical Specification function . Each surveillance requirement specifies the tests to be performed, the acceptance criteria, and the testing frequency.
Surveillance testing is typically required at some specified frequency such as 7 days, 31 days or 18 months. For a few Technical Specifications, the surveillances are linked to an initiating event or specific plant condition. Eleven of the HNP Technical Specifications specify both a frequency of 18 months and an additional modifier that the testing be done while the unit is shutdown. For many of these surveillances the addition of the shutdown modifier imposes unnecessary conditions on the performance of at least portions of the testing and results in duplicative testing.
HNP is proposing to revise eight of these surveillances to delete the conditional statement that the testing be performed while the unit is shutdown.
Basis This proposed change permits HNP to eliminate unnecessary repetitive testing. The TS surveillances affected by this request are listed in the following table:
Page El-1 9703240i32 9703i7 PDR ADQCK 05000400 p PDR
ENCLOSURE TO SERIAL: HNP-97-056 TECHNICAL SPECIFICATION SURVEILLANCE 3.1.2.2 Reactivity Control Systems Flow Paths- Boration Flow Path Valve Operating 4.1.2.2.c Verification 3.5.2 Emergency Core Cooling Systems ECCS Subsystems - Tavg 2 350'F 4.5.2.e ECCS Pumps and Valves 3.6.2 Containment Depressurization and Cooling Systems 4.6.2.1.c Containment Spray - Pumps and Containment Spray System Valves Spray Additive System 4.6.2.2.c Containment Spray - Spray Additive 3.6.3 Containment Isolation Valves 4.6.3.2 Containment Isolation Valves 3.7.1.2 Plant Systems Auxiliary Feedwater System 4.7.1.2.1. AFW Pumps and Valves b
3.7.3 Plant Systems Component Cooling Water System 4.7.3.b CCW Pumps and Valves 3.7.4 Plant Systems Emergency Service Water System 4.7.4.b ESW Pumps and Valves The wording of the Technical Specification surveillances listed above implies that all of the testing be performed during shutdown (i.e. plant is not in MODE 1 or 2). This condition implies that HNP should not take credit for equivalent tests on some components which are currently performed at power to comply with other surveillances. Therefore complying with this condition leads to unnecessary test repetition during refueling outages. One example of this is the testing of Engineered Safeguards Features Slave Relays. These tests are performed quarterly on all slave relays except those which are specifically exempted in the Technical Specifications because of the significant adverse consequences ifthey were operated while at power. The quarterly tests cycle approximately 140 valves which are required to actuate on various Engineered Safety Function signals, including containment isolation valves. However, due to the conditional statement in the surveillances listed above that their testing be performed while the unit is shutdown, there is an implication that the results of the quarterly testing cannot be used to meet a portion of the requirements of the 18 month tests even though the quarterly tests are functionally identical to a portion of the 18 month test. Without the "during shutdown" condition, it is clear that the scope of the 18 month testing may be reduced by eliminating unnecessary and repetitive testing of most of these valves.
Page El-2
ENCLOSURE TO SERIAL: HNP-97-056 Elimination of the shutdown requirement will not exclude any Technical Specification required component or function from surveillance testing, nor will it change any surveillance frequency.
It clarifies the acceptability of eliminating duplicate te'sting by allowing HNP the flexibilityto take credit for tests which are currently being performed at power in accordance with the Technical Specifications.
Of the approximately 45 references in the HNP Technical Specifications to an 18 month surveillance interval, only 11 refer to both the frequency and specify a shutdown condition. The new Standard Technical Specifications for Westinghouse Plants, NUREG-1431, Rev. 1 include specifications equivalent to seven of the eight specifications listed above, and all of them have unrestricted frequencies of 18 months. The NUREG-1431, Rev. 1 bases for these specifications do contain statements on the desirability of performing many of these tests while shutdown.
However, these statements refer to the overall testing and do not preclude taking credit for testing already performed for specific components, or from evaluating the specific plant conditions required for each test. There are surveillances in NUREG-1431, Rev. 1 which do have additional restrictions to the frequency similar to the conditional statements in the current HNP Technical Specifications, but HNP is not requesting changes to these surveillances.
Removal of the shutdown condition from the requested sur veillances will have no detrimental effect on the surveillance program, since the obligation to determine the plant conditions required to safely and prudently perform the required surveillance tests on all affected components remains an HNP responsibility. Some of the surveillances affected by this proposed change will continue to be performed in whole or in part during periods of plant shutdown. However, the testing conditions will be based on an evaluation of specific HNP conditions with respect to the individual components, HNP plant design, and the requirements of the specific test.
Conclusions The proposed change revises eight specifications for 18 month tests to delete a conditional statement that the testing be done while the unit is shutdown. The proposed changes will clarify that HNP may take credit for tests on some components which are performed while the unit is at power. The proposed change does not authorize the performance of any tests at power; it does allow HNP to evaluate the conditions required to safely test components and perform the tests in accordance with those evaluations.
,Page E1-3
ENCLOSURE TO SERIAL: HNP-97-056 ENCLOSURE2 SHEARON HARMS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT DELETION OF SHUTDOWN REQUIRMENT FROM SELECTED SURVEILLANCES 10 CFR 50.92 EVALUATION The Commission has provided standards in 10 CFR 50.92(c) for determining whether a significant hazards consideration exists. A proposed amendment to an operating license for a facility involves no significant hazards consideration ifoperation 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, (2) create the possibility of a new or different kind of accident from any accident previously evaluated, or (3) involve a significant reduction in a margin of safety. Carolina Power & Light Company has reviewed this proposed license amendment request and determined that its adoption would not involve a significant hazards determination. The bases for this determination are as follows:
Pro osed Chan e Carolina Power & Light Company proposes to revise surveillances 4.1.2.2.c, 4.5.2.e, 4.6.2.1.c, 4.6.2.2.c, 4.6.3.2, 4.7.1.2.1.b, 4.7.3.b, and 4.7.4.b to delete specific restrictions in the text of the surveillances that the tests must be done while the unit is shutdown.
Basis This change clarification does not involve a significant hazards consideration for the following reasons:
The proposed amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated.
The proposed changes permit HNP to evaluate the conditions required to safely perform a test, but the changes do not directly affect the functioning or operation of any plant equipment. Since no equipment operation is involved there is no increase in the probability or consequence of any previously identified accident.
Page E2-1
ENCLOSURE TO SERIAL: HNP-97-056
- 2. The proposed amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated.
The proposed changes to the conditional statements on the surveillance frequencies do not involve any physical alterations or additions to plant equipment or alter the manner in which any safety-related system performs its function or is operated. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
The proposed amendment does not involve a significant reduction in the margin of safety.
The proposed changes to the conditional statements on the surveillance frequency allows HNP to evaluate the conditions needed to safely perform the required testing. There is no change in the frequency of testing or in the testing which is required. There is no change in the responsibility of HNP to perform tests in a safe and responsible manner, and any changes to procedures will have to be individually evaluated to ensure that they do not reduce the margin of safety.
Page E2-2
ENCLOSURE TO SERIAL: HNP-97-056 ENCLOSURE3 SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT DELETION OF SHUTDOWN REQUIRMENT FROM SELECTED SURVEILLANCES ENVIRONMENTALCONSIDERATIONS 10 CFR 51.22(c)(9) provides criterion for and identification of licensing and regulatory actions eligible for 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 amendment would not: (1) involve a significant hazards consideration; (2) result in a significant change in the types or significant increase in the amounts of any effluents that may be released offsite; (3) result in a significant increase in individual or cumulative occupational radiation exposure. Carolina Power & Light Company has reviewed this request and determined that the proposed amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment needs to be prepared in connection with the issuance of the amendment. The basis for this determination follows:
Pro osed Chan e Carolina Power & Light Company proposes to revise surveillances 4.1.2.2.c, 4.5.2.e, 4.6.2.1.c, 4.6.2.2.c, 4.6.3.2, 4.7.1.2.1.b, 4.7.3.b, and 4.7.4.b to delete specific restrictions in the text of the surveillances that the tests must be done while the unit is shutdown.
Basis The change meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) for the following reasons:
- 1. As demonstrated in Enclosure 2, the proposed amendment does not involve a significant hazards consideration.
- 2. The proposed amendment does not result in a significant change in the types or significant increase in the amounts of any effluents that may be released offsite.
Page E3-1
ENCLOSURE TO SERIAL: HNP-97-056 The proposed change does not involve, any new equipment or require existing systems to perform a different type of function than they are currently designed to perform. The change does not introduce any new effluents or increase the quantities of existing effluents. As such, the change cannot affect the types or amounts of any effluents that may be released offsite.
The proposed amendment does not result in a significant increase in individual or cumulative occupational radiation exposure.
The proposed change does not result in any physical plant changes or new surveillances which would require additional personnel entry into radiation controlled areas.
Therefore, the amendment has no effect on either individual or cumulative occupational radiation exposure.
Page E3-2
ENCLOSURE TO SERIAL: HNP-97-056 ENCLOSURE4 SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT DELETION OF SHUTDOWN REQUIRMENT FROM SELECTED SURVEILLANCES PAGE CHANGE INSTRUCTIONS Removed Pa e Inserted Pa e 3/4 1-8 3/4 1-8 3/4 5-5 3/4 5-5 3/4 6-11 3/4 6-11 3/4 6-12 3/4 6-12 3/4 6-15 3/4 6-15 3/4 7-5 3/4 7-5 3/4 7-11 3/4 7-11 3/4 7-12 3/4 7-12
ENCLOSURE TO SERIAL: HNP-97-056 ENCLOSURE5 SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT DELETION OF SHUTDOWN REQUIRMENT FROM SELECTED SURVEILLANCES TECHNICAL SPECIFICATION PAGES
R ACTIVITY CONTRO YS HS LIHITING CONDITION FOR OPERATION 3.1.2.'2 At least two of the following three boron injection flow paths shall be OPERABLE:
- a. The flow path from the boric acid tank via a boric acid transfer pump and a charging/safety injection pump to the Reactor Coolant System (RCS). and
- b. Two flow paths from the refueling water storage tank via charging/
safety injection pumps to the RCS.
~CTIOM:
With only one of the above required boron 1njection flow paths to the RCS OPERABLE. restore at least two boron inject1on flow paths to the RCS to
'PERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY and borated to a SHUTDOWN HARGIN as specif1ed in the CORE OPERATING LIHITS REPORT (COLR), plant
,procedure PLP-106 at 200'F w1thin the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore at least two flow paths to OPERABLE status within the next 7 days or be 1n HOT SHUTDOWN within the next 6.hour s.
SURVEILLANCE REQUIREHENTS 4.1.2.2 At least two of the above requ1red flow paths shall be demonstrated OPERABLE:
- a. At least once per 7 days by verifying that the temperature of the flow path between the boric acid tank and the charging/safety inject1on pump suction header tank 1s greater than or equal to 65 F when a flow path from the boric acid tank is used:
- b. At least once per 31 days by ver1fying that each valve (manual, power-operated, or automatic) 1n the flow path that 1s not locked.
sealed, or otherwise secured in position, is in its correct pos1t1on; c ~ At least once per 18 months in hut by ver1fying that each automat1c valve in the flow a ua es o 1ts correct position on a safety 1nject1on test s1gnal: and
- d. At least once per 18 months by verifying that the flow path required by Specif1cation 3.1.2.2a. del1vers at least 3D gpm to the RCS.,
SHEARON HARRIS - UNIT 1 3/4 1-8 Amendment No.P9
EMERGENCY COR COOLINC SYSTEMS SURVEII.LANCE RE UIREMENTS (Continued) d ~ At lease once per 18 monchs by:
Verifying aucomacic interlock action of che RHR syscem fram the R'eactor Coolant System by ensuring that uich a simulated or actuaL Reactor Coolant Syscem pressure signal greater than or equal co 425 psig che interlocks prevent the valves Erom being opened.
- 2. A visual inspeccion oE each containment sump and verifying chat the subsystem suction inlecs are noc restricted by debris and chat the sump components (trash racks, screens, etc.) shoM no evidence of structural, distress or abnormal c rrosion.
- e. At least once per 18 manths l by:
- 1. Verifying chac each aucomatic valve in che floM pach actuates co ics correct position on saEecy injeccion actuation test signal and on safety injection sMitchover to concainmenc sump fram an RMST Lo-t.o level tesc signal, and
- 2. Verifying chat each of che folloMing pumps start, aucomacically upon receipt of a safety injection actuation test signal:
a) Charging/safety injection pump>
b) RHR pump.
By verifying thee each of the folloMing pumps develops the required difEerenciaL pressure Mhen cested pursuant to Specification 4.0.5:
- 1. Charging/safety injectian pump (Refer co Speci tication 4.1.'.4)
- 2. RHR pump > 100 psid ac a floe race of ac lease 3663 gpm.
g ~ By verifying that the locking mechanism is in place and locked for the Eo 1 loving Hi gh Head ECCS throe tie va ives s L. within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Eolloving completion of each valve stroking operation or maincenance on the valve Mhen che ECCS subsyscems are required co be OPERABLE, and 2, ht least once per 1S months.
SHEAROH HARRIS UNIT 1 3/4 5-5 Amendment No ~
CONTAINMENT SYSTEMS 3/4. 6. 2 OEPRESSUR IZATION AND COOLING SYSTEMS CONTAINMENT SPRAY SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2. 1 Two independent Containment Spray Systems shall be OPERABLE with each Spray System capable of taking suction from the RWST and transferring suction to the containment sump.
APPLICABILITY: MODES l. 2. 3, and 4.
ACTION:
With one Containment Spray System inoperable. restore the inoperable Spray System to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore the inoperable Spray System to OPERABLE status within the next 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
Refer also to Specification 3.6.2.3 Action.
SURVEILLANCE REQUIREMENTS 4.6.2. 1 Each Containment Spray System shall be demonstrated OPERABLE:
At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked.
sealed. or otherwise secured in position. is in its correct position;
- b. By verifying that. on an indicated recirculation flow of at least 1832 gpm, each pump develops a differential pressure of greater than or equal to 186 psi when tested pursuant to Specification 4.0.5;
- c. At least once per 18 months d ing hut wn by:
- 1. Verifying that each automatic valve in the flow path actuates to its correct position on a containment spray actuation test signal and
- 2. Verifying that each spray pump starts automatically on a containment spray actuation test signal.
- 3. Verifying that, coincident with an indication of containment spray pump running, each automatic valve from the sump and RWST actuates to its appropriate position following an RWST Lo-Lo test signal.
At least once per 10 years by performing an air or smoke flow test i through each spray header and verifying each spray nozzle is unobstructed.
SHEARON HARRIS - UNIT 1 3/4 6-11 Amendment No.M
LIMITING CONDITION FOR OPERATION 3,6.2.2 The Spray Additive System shall be OPERABLE with:
a ~ A Spray Additive Tank containing between 28 and 30 weight % NaOH and a contained volume of between 3268 and 3964 gallons which will be ensured by maintaining an indicated level between 92% and 96%,
and
- b. Two spray additive eductors each capable of adding NaOH solution from the chemical additive tank to a Containment Spray System pump flow.
MODES 1, 2, 3, and 4.
MGQE:
With the Spray Additive System inoperable, restore the system to OPERABLE stacus within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />s:
rescore che Spray Additive System to OPERABLE stacus within the next 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in COLD SHUTDOWN within che following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVE LLANC U NTS I
4.6.2.2 The Spray Additive System shall be demonstrated OPERABLE:
- a. At least once per 31 days by verifying that each valve (manual, power-operated,'or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position;
- b. At lease analysis.
once per 6 months by:
- 1. Verifying the contained solution volume in the tank, and
- 2. Verifying the concentration of the NaOH solution by chemical C ~ At least once per 18 months by verifying chat each automatic valve in the flow path actuates to i,ts correct position on a containment spray or containment isolation phase A teat signal as applicable; and
- d. ht, least once per 5 years by verifying each eductor flow rate is between 19.5 and 20.5 gpm, using the RWST as the test source containing at least 436,000 gallons of water.
SHEARON HARRIS - UNIT 1 3/4 6-12 Amendmenc No.~
CONTAINHENT SYSTENS COHTAIHMENT ISOLATION VALVES SURVEILLANCE REQUIRENENTS (Continued)
~ 4.6.3.2 S WN o Each t
REFU isolacion valve shall INC ac lease be demonstraced OPERABLE du once per 18 months by:
ng he
- a. Verifying thac on a Phase "A" Isolation test, signal, each Phase "A" isolacion valve actuates co ics isolation posicion;
- b. Verifying chat on a Phase "B" Isolation test signal, each Phase "B" isolacion valve actuates to ics isolation posicion; and
- c. Verifying that on a Containmenc Ventilacion Isolation tesc signal, each noimal, preentry purge makeup and exhausc, and concainmenc vacuum relief valve actuates co ics isolacion position, and
- d. Verifying thar., on a Safety Injection "S" "S" test signal, each concainmenc isolation valve receiving an signal actuates co its isolation posicion, and
- e. Verifying chat, on a Hain Steam Isolation tesc signal, eath main steam isolation valve actuates co its isolation position, and
- f. Verifying chat, on a Hain Feedwater Isolation test signal, each feedwacer isolation valve actuates to its isolacion position.
4.6.3.3 The isolacion r.ime of each pouer-operated or automatic valve shall be dececmined to be within ics limit specified in the Technical Specification Equipmenc List Program, plant proredure PLP-I06, when cesced pursuant to Specification 4.0.5.
SHEAROH HARRIS - UNIT l 3/4 6-l5 Amendment Ho. 25
PLANT SYSTEMS AU." IL IARY FEED SYSTEM r
SURVEILLANCE REQUIREMENTS (Continued)
Z. Demonstrating that the steam turbine - driven pump satisfies performance requirements by either:
- +**
NOTE: The provisions of Specification 4.0.4 are not applicable for entry into HOOE 3.
a) Verifying the pump develops a differential pressure that (when temperature - compensated to 70'F) is greater than or equal to 1433 psid at a recirculation flow of greater than or equal to 90 gpm (45 KPPH) when the secondary steam supply pressure is greater than 210 psig, or b) Verifying the pump develops a differential pressure that (when temperature - compensated to ?O') is greater than or equal to 1400 psid at a flow rate of greater than or equal to 430 gpm (215 KPPH) when the secondary steam supply pressure is greater than 280 psig.
- 3. Verifying by flow'r position check that each valve (manual, power operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position is in its correct position; and
- 4. Verifying that the isolation valves in the suction line from the CST are locked open.
- b. At least once per I& months n by:
Verifying that each motor-driven auxiliary feedwater pump starts automatically, as designed, upon receipt of a test signal and that the respective pressure control valve for each motor-driven pump and each flow control valve with an auto-open feature respond as requ'ired;
- 2. Verifying that the turbine-driven auxiliary feedwater pump starts automatically, as designed, upon receipt of a test signal. .The provisions of Specification 4.0.4 are not applicable for entry into HOOE 3; and
- 3. Verifying that the motor-operated auxiliary feedwater
~
isolation valves and flow control valves close as required upon receipt of an appropriate test signal for steamline differential pressure high coincident with main steam isolation.
SHEARON HARRIS - UNIT I 3/4 7-5 Amendment No. M
3/4.7.3 ~NENT COOLING MATER SYSTEH LIMITIHG CONOITION FOR OP'ERATION 3.7.3 At .least two component 'cooling water (CCN) pumps~, heat exchangers and .
essentfal flow paths shall be OPERABLE.
APPLIQABILITY: HOOKS I, 2, 3, and 4.
ACTIONS Nfth only one component coolfng water flow path OPERABLE, restore at least two flow paths to OPERABLK status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be fn at least HOT STANOBY wfthfn the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and fn COLO SHUTQOWN wfthfn the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REOUIREHENTS 4.7.3 At least two component coolfng water flow paths shall be demonstrated OPERABLE:
- a. At least once per 3I days by verffyfng that each valve (manual, power operated, or automatfc) servfcfng safety-related equipment that is not locked, sealed, or otherwfse secured fn posftfon is in its correct posftfon; and
- b. -
At least once per IS months verf fyfng that:
- 1. Each autoaatfc valve servfcfng safety related equfpment or fsolatfng non-safety related ~nants actuates to fts corr'ect po¹ftfon on a Safety Ingectfon teat sfgnal, and Z. Each Cosponent Coolfng Niter Systaa starts autoeatf cally p~ requfred to be on a Safety In)ectf on test sf gnal.
OPERABLE 3 Each aQfAsltfc valve serving the gross faf led fuel detector actuate¹ to fts correct posftfon on a Low Surge Tank Level te¹C sf gnat.
'The breake~ for CN pump IC-SAB shall not be racked fnto efther pow'er source (SA or SS) unless the breaker fs racked out.
f~ the applfcable CCM p~ (IA-SA or H-SB)
SHEARON HARRIS - .UNIT I
PLANT SYSTEMS e 3/4. l. 4 EMERGENCY SERVICE MATER SYSTEM LIMITING CONOITION FOR OPERATION 3.7. 4 At least two independent emergency service water loops shall be OPERABLE.
APPLICABILITY: MOOES 1, 2, 3, and 4.
ACTION:
Nth only one emergency service ~ater loop OPERABLE, restore at'least two loops to OPERABLE status withfn 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be fn at least HOT STANOBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and fn COLO SHUTMWN wfthfn the t'ollowfng 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE RE UIREMENTS 4.7.4 At 1east two emergency service water loops shall be demonstrated OPERABLE:
- a. At least once per 31 days by verifying that each valve (manual, power operated, or automatfc) servicing safety-related equipment .hat is not locked, sealed, or otherwise secured in positfon is in its correct posftfon; and
- b. At least once per 18 months by verf lying that:
- 1. Each autoeatfc valve servfcfng safety related equipment or fsolatfng non-safety portions of'he systae actuates to its correct posftfon on a Safety.In)ectfon test signal, and
- 2. Each emergency servfce water puap and each emergency service water booster pump starts autoaatfcally on a Safety Injection test sfgnal.
SHEARQN HARRIS UNIT 1 3/4 7-12
REACTIVITY CONTROL S EMS FLOW PATHS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.2 At least two of the following three boron injection flow paths shall be OPERABLE:
- a. The flow path from the boric acid tank via a boric acid transfer pump and a charging/safety injection pump to the Reactor Coolant System (RCS), and
- b. Two flow paths from the refueling water storage tank via charging/
safety injection pumps to the RCS.
APPLICABILITY: MODES 1, 2, and 3.
ACTION:
With only one of the above required boron injection flow paths to the RCS OPERABLE, restore at least two boron injection flow paths to the RCS to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY and borated to a SHUTDOWN MARGIN as specified in the CORE OPERATING LIMITS REPORT (COLR), plant procedure PLP-106 at 200'F within the next 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />s: restore at least two flow paths to OPERABLE status within the next 7 days or be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIREMENTS
- 4. 1.2.2 At least two of the above required flow paths shall be demonstrated OPERABLE:
- a. At least once per 7 days by verifying that the temperature of the flow path between the boric acid tank and the charging/safety injection pump suction header tank is greater than or equal to 65'F when a flow path from the boric acid tank is used;
- b. At least once per 31 days by verifying that each valve (manual, power -operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position;
- c. At least once per 18 months by verifying that each automatic valve /
in the flow path actuates to its correct position on a safety injection test signal: and
- d. At least once per 18 months by verifying that the flow path required by Specification 3. 1.2.2a. delivers at least 30 gpm to the RCS.
SHEARON HARRIS - UNIT 1 3/4 1-8 Amendment No.
EMERGENCY CORE COOLI SYSTEMS
'SURVEILLANCE REQUIREMENTS (Continued)
- d. At least once per 18 months by:
- 1. Verifying automatic interlock action of the RHR system from the Reactor Coolant System by ensuring that with a simulated or actual Reactor Coolant System pressure signal greater than or equal to 425 psig the interlocks prevent the valves from being opened.
- 2. A visual inspection of the containment sump and verifying that the subsystem suction inlets are not restricted by debris and that the sump components (trash racks, screens.
etc.) show no evidence of structural distress or abnormal corrosion.
- e. At least once per 18 months by:
- 1. Verifying that each automatic valve in the flow path actuates to its correct position on safety injection actuation test signal and on safety injection switchover to containment sump from an RWST Lo-Lo level test signal. and
- 2. Verifying that each of the following pumps start automatically upon receipt of a safety injection actuation test signal:
a) Charging/safety injection pump, b) RHR pump.
By verifying that each of'he following pumps develops the required differential pressure when tested pursuant to Specification 4.0.5:
- 1. Charging/safety injection pump (Refer to Specification 4.1.2.4)
- 2. RHR pump ~ 100 psid at a flow rate of at least 3663 gpm.
- g. By verifying that the locking mechanism is in place and locked for the following High Head ECCS throttle valves:
- 1. Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following completion of each valve stroking operation or maintenance on the valve when the ECCS subsystems are required to be OPERABLE, and
- 2. At least once per 18 months.
SHEARON HARRIS - UNIT 1 3/4 5-5 Amendment No.
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CONTAINMENT SYSTEMS 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT SPRAY SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2. 1 Two independent Containment Spray Systems shall be OPERABLE with each Spray System capable of taking suction from the RWST and transferring suction to the containment sump.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
With one Containment Spray System inoperable, restore the inoperable Spray System to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBV within the next 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />s: restore the inoperable Spray System to OPERABLE status within the next 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in COLD SHUTDOWN within the following 30 hour3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> s.
Refer also to Specification 3 '.2.3 Action.
SURVEILLANCE REQUIREMENTS 4.6.2. 1 Each Containment Spray System shall be demonstrated OPERABLE:
At least once per 31 days by verifying that each valve (manual.
power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position. is in its correct position;
- b. By verifying that. on an indicated recirculation flow of at least 1832 gpm, each pump develops a differential pressure of greater than or equal to 186 psi when tested pursuant to Specification 4.0.5;
- c. At least once per 18 months by:
- 1. Verifying that each automatic valve in the flow path actuates to its correct position on a containment spray actuation test signal and
- 2. Verifying that each spray pump starts automatically on a containment spray actuation test signal.
- 3. Verifying that. coincident with an indication of containment spray pump running, each automatic valve from the sump and RWST actuates to its appropriate position following an RWST Lo-Lo test signal.
At least once per 10 years by performing an air or smoke flow test through each spray header and verifying each spray nozzle is unobstructed.
SHEARON HARRIS - UNIT 1 3/4 6-11 Amendment No.
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V CONTAINMENT SYSTEMS SPRAY ADDITIVE SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.2 The Spray Additive System shall be OPERABLE with:
- a. A Spray Additive Tank containing between 28 and 30 weight X NaOH and a contained volume of between 3268 and 3964 gallons which will be ensured by maintaining an indicated level between 92K and 96K, and
- b. Two spray additive eductors each capable of adding NaOH solution from the chemical additive tank to a Containment Spray System pump flow.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
With the Spray Additive System inoperable, restore the system to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />s:
restore the Spray Additive System to OPERABLE status within the next 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.2.2 The Spray Additive System shall be demonstrated OPERABLE:
- a. At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position;
- b. At least once per 6 months by:
- l. Verifying the contained solution volume in the tank, and
- 2. Verifying the concentration of the NaOH solution by chemical analysis.
- c. At least once per 18 months by verifying that each automatic valve f in the flow path actuates to its correct position on a containment spray or containment isolation phase A test signal as applicable:
and
- d. At least once per 5 years by verifying each eductor flow rate is between 19.5 and 20.5 gpm, using the RWST as the test source containing at least 436,000 gallons of water.
SHEARON HARRIS - UNIT 1 3/4 6-12 Amendment No.
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CONTAINMENT SYSTEMS CONTAINMENT ISOLATION VALVES SURVEILLANCE REQUIREMENTS (Continued) 4.6.3.2 Each isolation valve shall be demonstrated OPERABLE at least bnce per 18 months by:
- a. Verifying that on a Phase "A" Isolation test signal, each Phase "A" isolation valve actuates to its isolation position;
- b. Verifying that on a Phase "B" Isolation test signal, each Phase "B" isolation valve actuates to its isolation position; and
- c. Verifying that on a Containment Ventilation Isolation test signal,,
each normal, preentry purge makeup and exhaust, and containment vacuum relief valve actuates to its isolation position, and
- d. Verifying that, on a Safety Injection "S" test signal, each containment isolation valve receiving an "S" signal actuates to its isolation position, and
- e. Verifying that, on a Main Steam Isolation test signal, each main steam isolation valve actuates to its isolation position, and Verifying that, on a Main Feedwater Isolation test signal, each feedwater isolation valve actuates to its isolation position.
4.6.3.3 The isolation time of each power-operated or automatic valve shall be determined to be within its limit specified in the Technical Specification Equipment List Program, plant procedure PLP-106, when tested pursuant to Specification 4.0.5.
SHEARON HARRIS - UNIT 1 3/4 6-15 Amendment No.
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PLANT SYSTEMS AUXILIARY FEEDWATER SYSTEM SURVEILLANCE REQUIREMENTS (Continued)
- 2. Demonstrating that the steam turbine - driven pump satisfies performance requirements by either:
NOTE: The provisions of Specification 4.0.4 are not applicable for entry into MODE 3.
a) Verifying the pump develops a differential pressure that (when temperature - compensated to 70'F) is greater than or equal to 1433 psid at a recirculation flow of greater than or equal to 90 gpm (45 KPPH) when the secondary steam supply pressure is greater than 210 psig, or b) Verifying the pump develops a differential pressure that (when temperature - compensated to 70'F) is greater than or equal to 1400 psid at a flow rate of greater than or equal to 430 gpm (215 KPPH) when the secondary steam supply pressure is greater than 280 psig.
- 3. Verifying by flow or position check that each valve (manual, ower operated, or automatic) in the flow path that is not ocked, sealed, or otherwise secured in position is in its correct position; and
- 4. Verifying that the isolation valves in the suction line from the CST are locked open.
At least once per 18 months by:
- 1. Verifying that each motor-driven auxiliary feedwater pump starts automatically, as designed, upon receipt of a hest signal and that the respective pressure control valve for each motor-driven pump and each flow control valve with an auto-open feature respond as required;
- 2. Verifying that the turbine-driven auxiliary feedwater pump starts automatically, as designed, upon receipt of a test signal. The provisions of Specification 4.0.4 are not applicable for entry into MODE 3; and
- 3. Verifying that the motor-operated auxiliary feedwater isolation valves and flow control valves close as required upon receipt of an appropriate test signal for steamline differential pressure high coincident with main steam isolation.
SHEARON HARRIS - UNIT 1 3/4 7-5 Amendment No.
PLANT SYSTEMS 3/4.7.3 COMPONENT COOLING WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.3 At least two component cooling water (CCW) pumps*. heat exchangers and essential flow paths shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
With only one component cooling water flow path OPERABLE, restore at least two flow paths to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.7.3 At least two component cooling water flow paths shall be demonstrated OPERABLE:
- a. At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) servicing safety-related equipment that is not locked. sealed. or otherwise secured in position is in its correct position; and At least once per 18 months by verifying that:
- 1. Each automatic valve servicing safety-related equipment or isolating non-safety-related components actuates to its correct position on a Safety Injection test signal, and
- 2. Each Component Cooling Water System pump required to be OPERABLE starts automatically on a Safety Injection test signal.
- 3. Each automatic valve serving the gross failed fuel detector actuates to its correct position on a Low Surge Tank Level test signal.
- The breaker for CCW pump 1C-SAB shall not be racked into either power source (SA or SB) unless the breaker from the applicable CCW pump (lA-SA or 1B-SB) is racked out.
SHEARON HARRIS - UNIT 1 3/4 7-11 Amendment No.
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PLANT SYSTEMS 3/4.7.4 EMERGENCY SERVICE WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.4 At least two independent emergency service water loops shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
With only one emergency service water loop OPERABLE. restore at least two loops to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.7.4 At least two emergency service water loops shall be demonstrated OPERABLE:
- a. At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) servicing safety-related equipment that is not locked. sealed. or otherwise secured in position is in its correct position; and
- b. At least once per 18 months by verifying that:
- 1. Each automatic valve servicing safety-related equipment or isolating non-safety portions of the system actuates to its correct position on a Safety Injection test signal, and 2 ~ Each emergency service water pump and each emergency service water booster pump starts automatically on a Safety Injection test signal.
SHEARON HARRIS - UNIT 1 3/4 7-12 Amendment No.
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