ML20217N351
| ML20217N351 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 04/30/1998 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20217N348 | List: |
| References | |
| NUDOCS 9805050299 | |
| Download: ML20217N351 (14) | |
Text
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ENCLOSURE 1 j
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT (SQN)
UNITS 1 and 2 l
l DOCKET NOS 327 AND 328 PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE TS-98-01 DESCRIPTION AND EVALUATION OF THE PROPOSED CHANGE I.
DESCRIPTION OF THE PROPOSED CHANGE TVA proposes to modify the Sequoyah Nuclear Plant (SON)
Units 1 and 2 Technical Specification (TS) 3.4.3.2 by revising Surveillance Requirement (SR) 4.4.3.2.1.b to allow meeting the surveillance by operating the valve through one complete cycle of full travel in Modes 3, 4,
or 5 with a steam bubble in the pressurizer.
Approval of this change supersedes the one-time footnote to Unit 1 SR 4.4.3.2.1, Therefore, this request deletes it.
The TS Bases are.also being revised to reflect'that representative conditions for l
PORV testing exist with a steam bubble in the pressurizer.
II.
REASON FOR THE PROPOSED CHANGE NRC required development of TSs for power-operated relief valve (PORV) testing in response to NRC Generic Letter 90-06.
Position 2 stated that stroke testing of PORVs should be performed during Mode 3 or Mode 4 and should not be performed during power operation.
In response to the GL, SON's TSs require that stroke testing be performed in Mode 4.
PORV testing for the ASME Code, Pump and Valve Inservice Testing Program, occurs in Mode 5, while testing of PORVs to demonstrate TS operability in accordance with SR 4.4.3.2.1.b occurs in Mode 4.
The TS testing duplicates much of the inservice testing that is required to be performed in Mode 5 (reactor coolant system (RCS) average temperature (Tavg] less than or equivalent to 200 F).
ASME Code testing is in Mode 5 since there is inherent risk in testing during operation from a potential loss of inventory i
standpoint and the potential risk of a PORV sticking open even though the block valve could be closed.
In addition, l
indirect remote position verification, achievable in Mode 5, is necessary since direct observation of stem j
movement is not available due to SQN's valve design.
Changing the mode requirement to allow Mode 5 performance provides flexibility in testing and eliminates duplication.
9805050299 980430 PDR ADOCK 05000327o P
PDR '
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Changing the. mode requirement to include Mode 3 allows additional flexibility within the bounds of the original NRC' guidance of GL 90-06.
III.
SAFETY ANALYSIS As stated in the TS Bases, the PORVs and steam bubble function to relieve RCS pressure during all design transients up to and including the design step load decrease with steam dump.
Operation of the PORVs minimizes the undesirable opening of the spring-loaded pressurizer code safety valves.
Each PORV has a remotely operated block valve to provide positive shutoff capability should a relief valve become inoperable.
The PORVs also function to remove noncondensables or steam-from the pressurizer.
Current TSs for controlling PORVs are a result of NRC GL 90-06.
GL 90-06 and NUREG-1316 provide little insight as to why Mode 3 or Mode 4 may be desired, except to suggest that it would better simulate temperature and pressure environmental conditions.
Requirements for Modes 3, 4, and 5 are basically defined by RCS Tavg.
Mode 3 requires 2 350'F; Mode 4 requires < 350 F, but >
0 200 F; and Mode 5 requires Tavg s 200 F.
However, the key.
parameter for PORV test is pressurizer pressure and temperature, not RCS Tavg.
Frequently in Mode 5, a
pressurizer bubble is developed for RCS pressure control.
As a result, representative conditions for PORV testing are present in Modes 3, 4, and 5 with a steam bubble.
A consideration for SQN is the specific PORV design.
The SON PORVs are Target Rock direct-acting, sclenoid-operated globe valves that use the opening of an internal pilot within the main disk to equalize pressure so that fluid force aids the solenoid force in opening the valve.
For this design, lower pressure (as is typical in lower modes) is a more conser.vative test of the valve and the valve actuator's ability to open the valve. _The SON PORV design makes testing.in a lower mode a more conservative test.
Therefore, expanding mode requirements to Modes 3, 4,
or 5, with a steam bubble from only Mode 4, is either conservative or within.the representative test requirements assessed in GL 90-06.
A possible factor related to testing in other than Mode 4 would be the effect on the low temperature overpressure protection (LTOP) TS 3.4.12.
TS 3.4.12 is applicable in Modes 4 and 5, and Mode 6 with the reactor vessel head on.
Since the current SR 4.4.3.2.1.b must be performed in Mode 4 and the ASME testing is performed in Mode 5, deletion of the mode restriction on SR 4.4.3.2.1.b would El-2
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allow the two tests to be performed together in the same mode lessening the time that potential LTOP impacts exist.
Testing in Mode 3 likewise lessons potential LTOP impacts.
The footnote to Unit 1 SR 4.4.3.2.1 is superseded by this request and its deletion will have no affect on plant operations.
In the June 29, 1992, Safety Evaluation, the NRC staff used site specific design factors in determining PORV Mode 5 testing acceptable for Comanche Peak Unit 1.
IV.
NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION TVA has concluded that operation of SON Units 1 and 2, in accordance with the proposed change to the TSs, does not involve a significant hazards consideration.
TVA's conclusion is based on its evaluation, in accordance with 10 CFR 50.91(a) (1), of the three standards set forth in 10 CFR 50.92(c).
A.
The proposed amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated.
The possibility of occurrence or the consequences for an accident or malfunction of equipment is not increased as the test conditions for the PORVs in Mode 5 are representative conditions based on a steam bubble being present, and testing in this mode is more conservative, if RCS pressure is less, since there is less fluid force to aid the solenoid force in opening the valve.
Testing in Modes 3 and 4 was the initial request of GL 90-06.
No changes are proposed to j
operation of the PORV block valves.
Offsite dose consequences are unchanged by this request.
B.
The proposed amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated.
A possibility for an accident or malfunction of a different type than any evaluated previously in SON's Final Safety Analysis Report is not created; nor is the possibility for an accident or malfunction of a different type.
A new test method is not required.
No new failure modes are introduced.
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C.
The proposed amendment does not involve a significant reduction in a margin of safety.
The margin of safety has not been reduced for testing in Mode 5 since the proposed test conditions are equal to,or more conservative, if RCS pressure is less, than those currently in use with existing SRs.
Testing in Modes 3 and 4 was-the initial' request of GL 90-06.
The results of'the accident analysis remain unchanged by this request.
V.
ENVIRONMENTAL IMPACT CONSIDERATION The proposed change does not involve a significant hazards consideration, a significant change in the types of or significant increase in the amounto of any effluents that may be released offsite, or a significant increase in individual or cumulative occupational radiation exposure.
Therefore, the proposed change meets _the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22 (c) (9).
Therefore, pursuant to 10 CFR 51.22(b), an i
environmental assessment of the proposed change is not j
required.
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ENCLOSURE 2 TENNESSEE VALLEY AUTHORITY
.SEQUOYAH PLANT (SQN)
UNITS 1 and 2 PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE TS-98-01 MARKE0 PAGES I.
AFFECTED PAGE LIST Unit 1 3/4 4-4a B3/4 4-2a Unit 2 3/4 4-8 B3/4 4-2a II.
MARKED PAGES See attached.
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4 REACTOR COOLANT SYSTEM RELIEF VALVES - OPERATING'
&;V LIMITING CONDITION FOR OPERATION 3.4.3.2 Two power relief valves (PORVs) and their associated block valves shall be OPERABLE.
R16 APPLICABILITY: MODES 1, 2,
and 3.
ACTION:
a.
Wit. one or' more PORV(s) inoperable, but capable of RCS pressure R115 cot "ol, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the PORV(s) to OPERABLE status or close the associated block valve (s); otherwise, 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 SHUTDOWN lR161 within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, b.
With one PORV inoperable and incapable of RCS pressure control, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the PORV to OPERABLE status or close R115 the associated block valve and remove power from the block valvet restore the.PORV to OPERABLE status within the following 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 /> and in HOT SHUTDOWN R161 within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, With both PORVs inoperable and incapable of RCS pressure control, c.
within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore each of the PORVs to OPERABLE status R115 or close their associated block valves and remove power from the
??1 block valves and 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 /> and HOT R161 g.-
SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
h.
d.
With one or more block valve (s) inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.:
(1)
'~
restore the block valve (s) to OPERABLE status, or close the block R115 valve (s) and remove power from the block valve (s), or close the
.PORV(s) and remove power from its associated solenoid valve (s); and (2) apply the ACTION b, or c. above, as appropriate, for the isolated PORV(s).
e.
The provisions of 1pecification 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.4.3.2.1 In addition to the requirements of Specification 4.0.5, each PORV
.chall be demonstrated OPERABLE at least once per 18 months by a.
Performance of a CHANNEL CALIBRATION, and b.
Operating the val gh_pne compinta cycig_of_ful travel lR161 during mode 8 # 3,4 er 5 wi h a steam bvWe hthe pq- -
lR234 t
w 4.4.3.2.2 Each block valve shall be demonstrated OPERABLE at least once per 92 fdays by operating the valve through one complete cycle of full travel.
For Unit 1 Cycle 9 peration only, this s eillance may be met V testing in Mode 5 with the ressurizer in saturat condition and tempera (re greater R234
~
than or equal t 420 degrees Fahrenhei Any entry into Mode uring Unit 1 Cycle 9 oper on will require perfo nce of this surveilla e in this mode.
January 13, 1998 SEQUOYAH - UNIT 1 3/4 4-4a Amendment Nos. 12, 105, 111, i
157, 230 l
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BASES-to cycle'.the valves when they have-been closed to comply'with the ACTION requirements.- This precludes the need to cycle the valves'with full system differential pressure or when ma_intenance-is being performed to' restore an inoperable PORV to operable status. __
& a de== buWie L %e er Testing of PORV t M0T SMUT 00= is required i.,..d:r te :f el:tr theT R161
'tempe,40ie end riweesie envir-eente; effects on "0"Ne.
Ia ;;ny.^0"! d::fga: 7
. testing-at COL" S;."JTDGWfis Econsidered to be a representative test for
~
- assessing POR1' performance under normal operating conditions. -Ir edd!ti:n,'
4esting POPYe ia un7 ggg7;c= wgg;; p7 ygg; ;g3:3 ::: 7 :: ef y:7y: p;7g,3; tty r for law-M ereture everpres;;r; pr;tectien.*~
3/4.'4.4 PRESSURIZER The limit on'the maximum water volume in the pressurizer _ assures that the parameter _is maintained within the normal steady ' state envelope of operation assumed in the'SAR.
The. limit is consistent'with the initial SAR assumptions.
The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> periodic surveillance is sufficient to ensure that the' parameter
.is restored to within its limit following expected transient operation.
The maximum water volume also ensures that a steam bubble'is formed and thus the.
RCS is not a hydraulically solid' system.
The requirement that 150 kw of pressurizer heaters and their associated controls be capable of being supplied
(-
electrical power from an emergency bus provides assurance that the plant will R16 be able to control reactor coolant pressure and establish natural circulation conditions.
3/4.4.5 STEAM GENERATORS The Surveillance Requirements for inspection of the steam generator tubes ensure that'the structural integrity of this portion of the RCS will be maintained.
The program for inservice inspection of steam generator tubes is based on a modification of Regulatory Guide 1.83, Revision 1.
Inservice inspection of steam generator tubing is essential in order to maintain surveillance of the conditions of the tubes'in the event that there is evidence of_ mechanical damage or progressive degradation due'to design, manufacturing errors, or inservice conditions that lead'to corrosion.
Inservice inspection of steam generator tubing also provides a means of~ characterizing the nature
.and cause of any tube degradation so ti.at corrective measures can be taken.
1 SEQUOYAH - UNIT 1 8 3/4 4-2a Amendment No. 12,
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157 March 30, 1992 i
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REACTOR COOLANT' SYSTEM RELIEF VALV S - OPERATING s.
LIMITING CONDITION Tux OPERATION 3.4.3.2 All power operated relief valves (PORVs) and their associated block valves shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, and 3.
ACTION:
y a.
With one or more PORv(s) inoperable, but capable of RCS pressure R101
' control, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the PORV(s) to OPERABLE status or close the' associated block valve (s); otherwise, 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 SHUTDOWN within the R147 following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
With one PORV inoperable and incapable of RCS pressure control, R101 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the PORV to OPERABLE status or closa the associated block valve and remove power from the block valve; restore the PORV to OPERABLE status within the following 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 /> and in HOT SHUTDOWN 7;I R
within the following 6. hours.
c.
With both PORVs inoperable and incapable of RCS pressure control, al ci within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore each of the PORVs to OPERABLE status or close their associated block valves and remove power from the block valves and 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 /> and HOT R147 SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> d.
With one or more block valve (s)-inoperable, within 1 hour:
(1) restore the block valve (s) to OPERABLE status, or close the block valve (s) and remove power from the block valve (s), or close g101 the PORV(s) and remove power from its associated solenoid valve (s);
and (-2) apply the ACTION b. or c. above, as appropriate, for the isolated PORV(s).
The provisions of Specification 3.0.4 are not applicable.
e.
. SURVEILLANCE REQUIREMENTS
'4.4.3.2.1 In addition to the requirements of Specification 4.0.5, each PORV shall be demonstrated OPERABLE at least once per 18 months by:
Performance of a CHANNEL CALIBRATION, and a.
Operating the val e t r gutnecompletecycje_ogulltravel b.
during mode'.47 3,51, or5 c.%a 5% AWie 6_%c pnaurmQ Each block valve shall be demonstrated OPERABLE at least once per 4.4.3.2.2 92 days by operating the valva'through one complete cycle of full travel.
+
SEQUOYAH - UNIT 2 3/4 4-8 Amendment No. 94, 101 147 March 30, 1992.
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1 REACTOR COOLANT. SYSTEM h
BASES 3/4.4.2 and 3/4!4.3 SAFET AND RE. LIEF VALVES (Continued)
. d.
Automatic ~ control of PORVs to control reactor' coolant system pressure.
This'3s a function'that reduces challenges to the code safety-valves. for. overpressure events.
. e..
Manual control of a block valve to, isolate a stuck-open PORV.
~
. SurveillanceLrequirements (SR) provide assurance that the PORVs and block
' valves ~can perform their functions. The block valves are exempt from the.SR to cycle the valves when they have been closed to comply with the ACTION.
requirements.
This~ precludes the necd'to cycle the valves with-fulljsystem.
differential pressure or.when. maintenance is being performed to restore'an inoperable PORV to operable status;
-(Enb shWWe 6 th W1 Testing of PORVs'-M TT 5",UT00Lt is r: et-ed <n Ord:r t :lelateth: f tei,&vi.tsre er,d pre::ar: nvir:n ;r,t:1 eff:3t: en POPVs.
Ia -eay Dgpy degjggg,r-Rl'4 7 -
4eetring :t COLO S:;UT00L f is m # considered to be'a representative test for
. assessing ^PORV performance'under normal operating conditions.
In :dditi:n, #.
to: ting POPV:
- 4. un7 ggt 79ew would pr: vide :dded usurance of velve caereb!'ity#
for !ew-+--a reter: :verpre::tre pr:t::tien. "
I' 3/4.4.4 PRESSURIZER 4
i
..Theilimit on the maximum water: volume in:the pressurizer assures that the
. parameter is maintained within the rormal steady state envelope of operation assumed in.the SAR. 1The limit is consistent with the initial SAR. assumptions.
- The 12~ hour periodic surveillance is sufficient to ensure that the parameter; is restored to within'its limit following expected transient operation.
The
-maximum water volume also ensures that a steam bubble is formed and thus the'
- RCS is not a hydraulically solid system.
The requirement that.150 kw.of.
pressurizer heaters M their associated controls be capable of being supplied electrical power from an emergency bus provides assurance that the plant will be?able to control. reactor coolant pressure and establish natural circulation
.condi.tions.
4 SEQUOYAH.- UNIT 2 B.3/4 4-2a Amendment No.
147 March 30, 1992
ENCLOSURE 3
.i-TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT (SQN)
UNITS 1 and'2-i PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE TS-98-01 REVISED PAGES I.
AFFECTED PAGE LIST Unit 1 3/4 4-4a
'B3/4 4-2a Unit 2 3/4 4-8 B3/4 4-2a l
II.
MARAED PAGES See attached.
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REACTOR COOLAFI' SYSTEM RELIEF VALVES - OPERATING LIMITING CONDITION FOR OPERATION 3.4.3.2 Two power relief valves (PORVs) and their associated block valves shall be OPERABLE.
' R16 APPLICABILITY: MODES 1, 2,
and 3.
ET&g:
a.
With one or more PORV(u) inoparable, but capable of RCS pressure R115 control, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the PORV(s) to OPERABLE status or close the associated block valve (s) ; otherwise, 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 SHUTDOWN lR161 within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
With one PORV' inoperable and incapable of.RCS pressure control, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the PORV to OPERABLE status or close R115 the associated block valve and remove power from the block valve; restore the PORV to OPERABLE status within the following 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 /> and in HOT SHUTDOWN R161 within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
With both PORVs inoperable and incapable of RCS pressure control, c.
within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore each of the PORVs to OPERABLE status R115 or close their associated block valves and remove power from the block valves and 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 /> and HOT R161 SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
d.
With one or more block valve (s) inoperable, within 1 hour:
(1) restore the block valve (s) to OPERABLE status, or close the block R115 valve (s) and remove power from the block valve (s), or close the PORV (s'; and romove power from its associated solenoid valve (s); and (2) apply the ACTION b. or c. above, as appropriate, for the isolated PORV(s).
The provisions of Specification 3.0.4 are not applicable.
e.
SURVEILLANCE REQUIREMENTS 4.4.3.2.1 In addition to the requirements of Specification 4.0.5, each PORV shall be demonstrated OPERABLE at least once per 18 months by:
a.
Performance of a CHANNEL CALIBRATION, and b.
Operating the valve through one complete cycle of full travel lR161 during Modes 3, 4,
or 5 with a steam bubble in the pressurizer.
l 4.4.3.2.2 Each block valve shall be demonstrated OPERABLE at least once per 92 days by operating the valve through one complete cycle of full travel.
SEQUOYAH - UNIT 1 3/4 4-4a Amendment Nos. 12, 105, 111, 157, 230, Q,
. A
s
. REACTOP COOLANT SYSTEM
' BASES to cycle the valves when they have been closed to comply with the ACTION requirements. This precludes the need'to cycle the valves with full system R161 differential pressure or when maintenance is being performed to restore an inoperable PORV to operable status.
Testing of PORVs with a steam bubble in the pressurizer is cons'idered to be a representive' test for assessing PORV performance under nornal operating conditions.
3/4.4.4 PRESSURItER The limit on the maximum water volume in the pressurizer assures that the parameter is maintained'within the normal steady state envelope of operation assumed-in the SAR.
The limit is consistent.with the initial SAR assumptions.
The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> periodic surveillance is sufficient to ensure that the parameter is restored to within its limit following expected transient operation. ~ The maximum water volume also ensures that a steam bubble is formed and thus the RCS is not a hydraulically solid system. The requirement that 150 kw of
. pressurizer heaters and ths.'r associated-controls be capable of being supplied electrical power from an emergency bus provides assurance that the plant will R16 be'able to control reactor coolant pressure and establish natural circulation conditions.
. 3 / 4 '. 4. 5 STEAM GENERATORS The Surveillance Requirements for inspection of the steam generator tubes ensure that the. structural integrity of this portion of the RCS will be maintained. The program for inservice inspection of steam generator tubes is based on a modificaticn of Regulatory Guide 1.83, Revision'l.
Inservice-l inspection of steam generator tubing is essential in. order to maintain-surveillance of the conditions of the tubes in the event that there is evidence of mechanical. damage or progressive degradation due to design, manufacturing errors, or inservice conditions that lead to corrosion.
Inservice inspection of steam generator tubing also provides a means of characterizing the nature and cause of any tube degradation so that corrective measures can be taken.
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.S2QUOYAH - UNIT 1 B 3/4 4-2a Amendment No. 12, 157 h
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REACTOR COOLANT SYSTEM RELIEF VALVES ' OPERATING LIMITING CONDITION FOR OPERATION 3.4.3.2 All power operated relief valves (PORVs) and their associated block
' valves-shall'be OPERABLE.
APPLICABILITY:' MODES.1, 2i and 3.
ACTIQN:
a.
With one or more PORV(s) inoperable, but capable of RCS pressure control, within 1_ hour either restore the PORV(s) to OPERABLE status R101 or close the associated block valve (s); otherwise, be in-at J oast 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 SHUTDOWN within the-R147 following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, b.
With one PORV inoperable and incapable of RCS pressure control, R101 j
within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the PORV to OPERABLE status or close the associated block valve and remove power from the block valver restore the PORV to OPERABLE status within the following 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 /> and in HOT SHUTDOWN within the R147 following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
c.
With both PORVs inoperable and incapable of RCS pressure' control, R101 l
within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore each of the PORVs to OPERABLE status or close their associated block valves and remove power from the block valves and 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 /> and HOT SHUTDOWN R147 within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, d.
With one or more block valve (s) inoperable, within 1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (1) restore the block valve (s) to OPERABLE status, or close the block valve (s) and remove power f rom the block valve (s), or close the R101 PORV (s) and remove power from its associated solenoid valve (s); and (2) apply'the ACTION b. or c. above, as appropriate, for the isolated PORV(s).
e.
The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS l
4.4.3.2.1 In addition to the requirements of Specification 4.0.5, each PORV i
l shall be demonstrated OPERABLE at least once per 18 months by:
a.
Performance of a CHANNEL CALIBRATION, and.
b.
Operating the valve through one complete cycle of full travel during Modes 3, 4,
or 5 with a steam bubble in the pressurizer.
l 4.4.3.2.2 Each block valve shall be demonstrated OPERABLE at least once p<r 92 days by operating the valve through one complete cycle of full travel.
SEQUOYAH - UNIT 2 3/4 4-8 Amendment Nos. 94, 101, 147
A REACTOR COOLANT SYSTEM BASES 3 /4. 4.2 and 3 /4.4. 3 SAFETY AND RELIEF' VALVES (Continued) d.
Automatic control of PORVs to control reactor coolant system pressure.
This in a function that reduces challenges to the code safety valves for overpressure events.
e.
Manual control of a block valve to isolate a stuck-open PORV.
R147 Surveillance requirements (SR) provide assurance that the PORVs and block ~
valves can perform their functions. The block valves are exempt from the SR to cycle the valves when they have been closed to comply with the ACTION requirements. This precludes the need to cycle the valves with full system i
differential pressure or when maintenance is being performed to restore an inoperable PORV to operable status.
Testing of PORVs with a steam bubble in the pressurizer is considered to be a representive test for assessing PORV performance under normal operating conditions.
'3/4.4.4 PRESSURIZER I
The limit on the maximum water volume in the pressurizer assures that the parameter is maintained.within the normal steady state envelope of operation assumed in the SAR.
The limit is consistent with the initial SAR assumptions.
The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> periodic surveillance is sufficient to ensure that the parameter is restored to within its limit following expected transient operation. The maximum water volume also enoures that a steam bubble is formed and thus the RCS is not a hydraulically solid system. The requirement that 150 kw of pressu rizer heaters and their associated controls be capable of being supplied electr ical power from an emergency bus provides assurance that the plant will be able to control reactor coolant pressure and establish natural circulation conditions.
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l i
l i
SEQUOYAH - UP7T 2 B 3/4 4-2a Amendment No. 147 i
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