ML19323G330

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Proposed Tech Spec Changes Re Mods to Several Action Statements to Allow Entry Into Modes 3 & 4 Before Completion of Actions Listed in O'Reilly 800429 Ltr
ML19323G330
Person / Time
Site: Sequoyah Tennessee Valley Authority icon.png
Issue date: 05/28/1980
From:
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML19323G327 List:
References
NUDOCS 8006020183
Download: ML19323G330 (8)
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Text

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ENCLOSURE 1 PROPOSED CHANGES TO SEQUOYAH NUCLEAR PLANT UNIT 1 TECHNICAL SPECIFICATIONS B006020\

EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.2 ECCS SUBSYSTEMS - T,y Greater Than or Equal to 350 F LIMITING CONDITION FOR OPERATION 3.5.2 Two independent ECCS subsystems shall be OPERABLE with each subsystem comprised of:

a. One OPERABLE centrifugal charging pump,
b. One OPERABLE safety injection pump,
c. One OPERABLE residual heat removal heat exchanger,
d. One OPERABLE residual heat removal pump, and
e. An OPERABLE flow path capable of taking suction from the refueling water storage tank on a safety injection signal and automatically transferring suction to the containment sump during the recirculation phase of operation.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

a. With one ECCS subsystem inoperable, restore the inoperable subsystem 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 HOT SHUTOOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b. In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describ-ing the circumstances of the actuation and the total accumulated actuation cycles to date. The current value of the usage factor ,

for each affected safety injection nozzle shall be provided in l this Special Report whenever its value exceeds 0.70. j

c. The provisions of specification 3.0.4 are not applicable for j entry into MODES 3 and 4 when systen inoperability has been determined solely on unresolved piping support or restraint def iciencies.

SURVEILLANCE REOUIREMENTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE: l l

a. .At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the following valves l are in the indicated positions with power to the valve operators removed:

SEQUOYAH - UNIT 1 3/4 5-5

EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.3 ECCS SUBSYSTEMS - T,yg Less Than 350*F LIMITING CONDITION FOR OPERATION 3.5.3 As a minimum, one ECCS subsystem comprised of the following shall be OPERABLE:

a. One OPERABLE centrifugal charging pump,
b. One OPERABLE residual heat removal heat exchanger,
c. One OPERABLE residual heat removal purrp, and
d. An OPERABLE flow path capable of taking suction from the refueling water storage tank upon being manually realigned and automatically transferring suction to the containment sump during the recirculation phase of operation.

APPLICABILITY: MODE 4.

ACTION:

a. With no ECCS subsystem OPERABLE becaus'e of the inoperability of either the centrifugal charging pump or the flow path from the refueling water storage tank, restore at least one ECCS subsystem to OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in COLD SHUTDOWN within the next 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />. .
b. With no ECCS subsystem OPERABLE because of the inoperability of either the residual heat removal heat exchanger or residual heat removal pump, restore at least one ECCS subsystem to OPERABLE status or maintain the Reactor Coolant System T""9 less than 350 F by use of alternate heat removal methods.
c. In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describ-ing the circumstances of the actuation and the total accumulated actuation cycles to date.
d. The provisions of specification 3.0.4 are not applicable for entry into MODES 3 and 4 when system inoperability has been determined solely on unresolved piping support or restraint deficiencies. '

SEQUOYAH - UNIT 1 3/4 5-9

CONTAINMENT SYSTEMS 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT SPRAY SY_ STEM 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:

a. With one containment spray system inoperable, restore the inoperable snray syst to to OPERABLE status uithin 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in 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' 4J hours or be in COLD SHUTDOLIN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
h. The provisions of specification 3.9.4 are not applicable for entry into MODES 3 and 4 when system inoperability has been determined solely on unresolved piping support or restraint deficiencies SURVEILLANCE REQUIREMENTS 4.6.2.1 Each containment spray system shall be demonstra*.ed 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. By verifying, that on recirculation flow, each pump develops a discharge pressure of greater than er eq 'al to 140 psig when tested pursuant to Specification 4.0.5.
c. At least once per 18 months during shutdown, by:
1. Verifying that each automatic valve in the flow path actuates to its correct position on a Containment Pressure--High-High test signal.
2. Verifying that each spray pump starts automatically on a Containment Pressure--High-High test signal.
d. At least once per 5 years by performing an air or smoke flow test through each spray header and verifying each spray nozzle is unobstructed.

SEQUOYAH - UNIT 1 3/4 6-16 i

CONTAINMENT SYSTEMS 3/4.6.3 CONTAINMENT ISOLATIOS VALVES LIMITING CONDITION FOR OPERATION 3.6.3.1 The containment isolation valves specified in Table 3.6-2 shall be OPERABLE with isolation times as shown in Table 3.6-2.

APPLICABILIl(: MODES 1, 2, 3 and 4.

ACTION:

a. Uith one or more of the isolation valve (s) snecified in Table 3.6-2 inoperable, maintain at least one isolation valve OPERACLE in cach affected penetration that is open and either:
1. Restore the inonerable valve (s) to OPERABLE status uithin 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or
2. Isolate each affected penetration uithin 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one deactivated automatic valve secured in the isolation position, or
3. Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one closed nanual valve or blind flange; or
4. Uc in at least HOT STA:iDSY 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 FHUTD0h'N within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
b. The provisions of specification 3.0.4 are not anplicable for entry into MODES 3 and 4 when system inoperability has been deternined solely on unresolved piping support or restraint deficiencien.

SURVEILLANCE REQUIREMENTS 4.6.3.1.1 The isolation valves specified in Table 3.6-2 shall be demonstrated OPERABLE prior to returning the valve to service after maintenance, repair or replacement work'is performed on the valve or its associated actuator, control or power circuit by performance of a cycling test and verification of isolation time.

4.6.3.1.2 Each isolation valve specified in Table 3.6-2 shall be demonstrated OPE 'BLE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 months by:

a. Verifying that on a Phase A containment isolation test signal, each Phase A isolation valve actuates to its isolation position.
b. Verifying that on a Phase B containment isolation test signal, each Phase B isolation valve actuates to its isolation position.

SEQUOYAH - UNIT 1 3/4 6-17

PLANT SYSTEMS AUXILIARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION

3. 7.1. 2 At least three independent steam ge-erator auxiliary feedwater pumps and associated flow paths shall be OPEi"E.E with:
a. Two feedwater pumps, each capable :f eing powered f rc= separate shutdown boards, and i b. One feedwater pump capable of beir; ::wered from en OPERABLE steam supply system.

APPLICARILITY: MODES 1, 2 and 3.

ACTION:

a. Uith one auxiliary feedwater punp inoperable, restore at least three auxiliary feedwater pumps (tuo capable of being novered from separate shutdown boards and one canable of being poucred by an OPERABLE steam supply systen) to OPERAELE 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 IIOT STA!!DBY within the ner.t 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> and in 110T SilUTDoh'N vithin the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b. The provisions of specification 3.0.4 are not applicable for.

entry into !! ODES 3 and 4 when systen inoperability has been i deternined solely on unresolved piping sunport or restraint deficiencies.

SURVEILLANCE REOUIREMENTS 4.7.1.2 Each auxiliary feedwater pump shal' :s :emonstrated OPERASLE:

a. At least once per 31 days by:
1. Verifying that each motor dr'..e pump cevelops a differential pressure of greater than or e:.1 to 1397 psid on recirculation flow.
2. Verifying that the steam tur:' s criven pump develops a differer.-

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tial pressure of greater tha..cr equal to 1183 psid on recircula-tion flow when the secondary 5 eim supply pressure is greater than 842 psig. The provisiers c' Specification 4.0.4 are not I applicable for entry into MO:E 3.

3. Verifying that each non-autort :: valve in the flow path that is not locked, sealed, or otter-ise secured in position, is in its correct position, and
4. Verifying that each automati: :: trol valve in the flo. patn is OPERABLE whenever the auxilit ,e 'eeuwater system is placed in automatic control or when ab:.a '0% of RATED THERMAL PO'a'ER. l l

l SEQUOYAH - UNIT 1 3/4 7-5 Amendment No. I JLER22tsea

ENCLOSURE 2 REASONS AND JUSTIFICATIONS FOR PROPOSED CHAFGES TO SEQULYAH NUCLEAR PLANT UNIT 1 TECHNICAL. SPECIFICATIONS i

ENCLOSURE

1. Specification 3.5.2, Page 3/4 5-5 TVA is in the process of verifying the adequacy of the as-built piping supports and restraints relative to the requirements of OIE Bulletin 79-14 and the letter from J. P. O'Reilly to H. G. Parris dated April 29, 1980. As specified in the letter, all required actions will be resolved before initial criticality. The proposed change will allow operating mode changes to take place with unresolved piping support or restroint deficiencies. As stated above, the deficiencies will be. resolved before initial criticality. Therefore, the requested cuange is onlr applicable during the period before initial criticality. At that t; me, the technical specification will be restored to its original form. TVA will notify the NRC of each instance that the provisions of this change are invoked.

Before initial criticality, no fission product inventory exists. The decay heat load is negligible. Therefore, operation in modes 3 or 4 for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> (as allowed by the ACTION statement) with unresolved piping support or restraint deficiencies poses no additional risk to the health and safety of the public.

2. Specification 3.5.5, Page 3/4 5-9 Same as above
3. Specification 3.6.2.1, Page 3/4 6-16 Same as above ,

i 4.

Specification 3.6.3.1, Page 3/4 6-17 Same as above

5. Specification 3.7.1.2, Page 3/4 7-5 i

Same as above 4

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