ML20155J718
| ML20155J718 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 06/14/1988 |
| From: | PUBLIC SERVICE CO. OF COLORADO |
| To: | |
| Shared Package | |
| ML20155J717 | List: |
| References | |
| P-88205, NUDOCS 8806210012 | |
| Download: ML20155J718 (14) | |
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Attachment 2 to P-88205 REVISED DRAFT TECHNICAL SPECIFICATIONS This attachment includes revised drafts of the following upgraded Technical Specifications:
3/4.6.5.2 - Revised to delete charcoal filter test exceptions after painting with low solvent paints, 2nd to define acceptable painting in the BASIS.
3/4.7.1.5 and 3/4.7.1.6 - Revised to require at least one operable EES Safety Valve per loop, for each boiler feed pump that is operating and supplying the EES Sections.
6.5.1.2 and 6.2.3.3 - Revised to reflect recent PSC re-organization, as discussed in P-88184.
The single margin marks that were shown in the May 25, 1988 draft have been retained. Double margin marks i.'dicate changes to the May 25, 1988 revised final draft.
8806210012 880614 PDR ADOCK 05000267 P DCD
Amendment No.
Page 3/4 6-48 PCRV AND CONFINEMENT SYSTEMS 3/4.6.5 REACTOR BUILDING CONFINEMENT JUN 131988 RfACTOR B'JILDING EXHAUST SYSTEM LIMITING CON 0! TION FOR OPERATION 3.6.5.2 The reactor builcing exhaust system shall be OPERABLE with:
- a. Reactor building internal pressure subatmospheric, and
- b. At least two of the three exhaust trains OPERABLE, with each train consisting of one exhaust fan (C-7301, C-7302, or C-73025) and an associated filter assemoly (F-7301, F-7302, or F-73025).
APPLICABILITY: POWER, LOW PCWER, STARTUP, SHUTDCWN and REFUELING
- ACTION:
- a. POWER, LOW POWER, and STARTUP
- 1. With reactor building interaal pressure greater than or eoual to atmosoneric cressure, restore it to suoatmospneric within 6 r:urs or be in at least SHUTCOWN within tne next 24 ours.
- 2. With only one exnaust train OPERABLE, restore an inocerable train to OPERABLE status within 7 days or be in at least SHUTCChN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,
- b. SHUT 00WN and REFUELING *
- 1. With tne reactor ouilding internal pressure greater than or eoual to atmoscheric oressure, immeciately susoend all ocerations involving CORE ALTERATIONS, control roc movements resulting in positive reactivity cnanges, or movement of IRRADIATED FUEL in the reactor building.
- 2. Witn only one exhaust train CPERABLE, restore an ino:erable train to CPERABLE status witnin 7 cays, or sus: enc all operations involving CCRE ALTERATIONS, centrol roc movements resulting in oositive reactivity enariges, or movement of IRRADIATED FUEL in the reactor cuilcing.
- Curing CCRE ALTERATICNS or narcling of IRRADIATED FUEL in tne reactor cuilcing.
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Amendment No.
Page 3/4 6-49 DRAFT SURVEILLANCE REQUIREMENTS lVN I 3 M 4.6.5.2 The reactor building exhaust system shall be demonstrated OPERABLE: ,
- 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 reactor building internal pressure is negative relative to atmospheric pressure.
- b. At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following significant fire, chemical release, or painting in any ventilation zone communicating with the system by:
- 1. ' Verifying that the exhaust system satisfies the in place penetration and bypass leakage testing acceptance criteria of less than 1?4 and uses the test procedure guidance in Regulatory Positions C 5.a. C.S.c, and C.S.d of Regulatory Guide
. 1.52, Revision 2, March 1978, and the flow rate is between 17,100 and 23,000 cfm per train,
- 2. Verifying within 31 days after removal, that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C 6.a of Regulatory Guide 1.52 Revision 2, March 1978, for a methyl iodide penetration of less than 10?4, and
- 3. Verifying a flow rate between 17,100 and 23,000 cfm per train during system operation when tested in accorcance with ANSI N510-1975.
- c. After every 4400 hours0.0509 days <br />1.222 hours <br />0.00728 weeks <br />0.00167 months <br /> of charcoal adsorber operation, by verifying within 31 days after removal, l that a laboratory analysis of a representative carbon l Sample obtained in accordance with Regulatory l Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978, for a methyl iodide penetration of less than 10?4.
DRAFT Amendment so.
Pago 3/4 6-50 JUN I 31988
- d. At least once ~ per 18 months by verifying that the pressure drop across the combined HEPA filters and charcoal adsorber , banks is less than 6 inches water gage while operating at a flow rate between 17,100 and 23,000 cfm for each filter train.
- e. After each complete or partial replacement of a HEPA filter bank, by verifying that the HEPA filter oank satisfies the in-place oenetration and bypass leakage testing acceptance criteria of less than 1% in accordance with ANSI N510-1975 for a 00P test aerosol wnile operating the system at a flow rate between 17,100 anc 23,000 cfm per train,
- f. After eacn complete or partial replacement of a charcoal adsorcer bank, by verifying that the charcoal adsorber bank satisfies the in-place cenetration and bypass leakage testing acceptance criteria of less than 1N in accordance with ANSI N510-1975 for a halogenated hydrocarbon refrigerant test gas while operating the system at a flow rate oetween 17,100 and 23,000 cfm per train,
DRAFT imendment No.
Page 3/4 6-51 JUN 131988 BASIS FOR SPECIFICATION LCO 3.6.5.2/SR 4.6.5.2 The reactor building exhcust filter system is designed to iilter the reactor building atmosphere prior to release to the facility vent stack during both normal and most accicent conditions of operation. Additional information is proviced in the BASIS for LCO 3.6.5.1/SR 4.6.5.1 and FSAR Section 6.2.4.
The system consists of tnree trains, two of which are normally in continuous operation (FSAR Section 6.2.3.2), with the third normally on stancey, The cesign flow rate for each train is 19,000 cfm. Allowing 10'., the minimum flow rate is 17,100 cfm. Based on cast performance data, a maximum flow rate of 23,000 cfm is also specified. One train is sufficient to maintain tne reactor building subatmospheric and thereby minimize unfiltered fission procuct release from the building.
With only one exnaust fan coerating, the ventilation system controls will snrottle fresh air supply to the air handler in order to recuce tne pressure.
The reactor building is maintained in a subatmospheric condition to ensure that all air leakage will be inward and to minimize unfiltered fission product release from the building.
The ventilation system was designed to maintain a subatmospheric condition of approximately 1/4 inch water gauge negative (FSAR 6.2.3.2). In actual practice, the reactor building pressure is normally indicated approximately 0.15 to 0.20 inches water gauge negative, cepending on building activity anc ventilation equipment cerfiguration. There is an alarm at approximately 0.03 inches water gauge negative, and the air supply will fully close if tne building pressure increases to atmosoneric (FSAR Section 14.7.3).
Bypass leakage and penetration for the enarcoal acsorcers and carticulate removal ef ficiency for HEPA filters are determined oy halogenated nycrocaroon and cioctyl entnalate (00P) resoectively. l The laboratory caroon samole test results incicate a radioactive metnyl iocice removal efficiency for exoectec accicent conditions. The filter /acsorcer eenetration and bypass acceotance limits in the surveillances are applicable cased on a HEPA filter efficiency of 9 5'. and charcoal acsorcer ef ficiency of 90'. assumed in the AEC staff's Safety Evaluation (Table 4.3, Safety Evaluation, Jan. 20, 1972; anc FSAR 5ection 14.12.3).
Tne surveillance 'recuencies soecifiec establish system cerformance caoacilities.
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DRAFT Amendment u .
Page 3/4 6-52 JUN I .') 1988 The activated carbon adsorber in the affected unit will be replaced if a representative sample fatis to pass the iodine removal efficiency test. Any HEPA filters found defective 4 will be replaced.
If fire, enemical release, or painting, occurs such that the HEPA filter or enarcoal adsorcer could become significantly contaminated from tne fumes, enemicals, or foreign materials, the same tests and sample analysis should be performed, as required, for operational surveillance. Reactor building exhaust tra i n( s) OPERABILITY snould be verified per SR 4.6.5.2.b following:
- 1. Painting with greater than 5 gallons of paint, irclucing water-case or ecuivalent paint, over the six-montn normal surveillance interval,
- 2. Any soray (aerosol generating) painting (incluces water-case or equivalent oaint),
- 3. Fires that exceed I hour in curation, oe 4 Any uncontrolled release / spillage of 5 gallons or more of any chemical material which could reasonably be exoected to interfere with the charcoal to adsorb methyl iccice.
A pressure drop across the combinec HEPA filter and charcoal adsorcer of less than 6 inenes of water gauge at the filter cesign flow rate will indicate that :ne filters and adsorbers are not clogged oy excessive amounts :f foreign matter.
Amendment No.
Page 3/4 742 DRAFT PLANT AND SAFE SHUT 00WN COOLING SUPPORT SYSTEMS JU,9 l 3 i988 3/4.7.1 TURBINE CYCLE SAFETY VALVES - OPERATING -
LIMITING CONDITION FOR OPERATION 3.7.1.5 a. At least one steam generator economizer-evsporater-superheater (EES) safety valve per loop (V-2214 V-27.15, '
V-2216, V-2245, V-2246, or V-2247) shall be OPERABLE [ for each boiler feed pump in operation supplying feedwcter to the EES sections, OPERABLE valve setpoints shall be in accordance with Table 4.7.1-1.*
- b. Both reheater safety valves (V-2225 and V-2262) 8 hall.me OPERABLE with setpoints in accordance with Table 4. 7.1 .
1.*
APPLICABILITY: POWER, LOW POWER and STARTUP l
ACTION: a. With one of the above required EES safety valves inoperable in eitner or both loops or with one -reheater safety valve inoperable, restore the required valve to OPERA 2LE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or restrict plant operation as follows:
- 1. With an E'S safety valve ir:cerable, restrict plant operation so that the number of boiler feed pumps in operation corresponds to the number of OPERABLE safety valves as required above.
- 2. With a reheater safety valve inoperable, be in at least SHUTOOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,
- b. The provisions of Specificatice 3 . 0.\ are not applicable.
SURVEILLANCE REQUIREMENTS 4.7.1.5 The superneater and reheater safety valves snar be demonstrated CPERABLE by testing in accordance with tne applicable ASME Coce reautrements to verify setpoints. Tne test frequency is specified in the ASME Code, and the lift settings are specifiec in Table 4.7.1-1.
Setpoint verification is not required until 7 days after achieving steady state olant operating con:itions at a cower ,
level above 50% RATED THERMAL POWER. s l
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{endmentNo.
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Page 3/4 7-13 U , ,
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( TABLE 4.7.1-1 -,
STEAM GENERATOR SAFETY VALVES VALVE NUMBER LIFT SETTINGS LOOP I V-2214 Less than or soual to 2917 psig V-2215 Less than or equal to 2846 osig
, V 2216 Less than or equal to 2774 psig x;, V-2225 Less than or-equal to 1133 psig ;
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LOOP II , ,
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V-2245 Less than or equal to 2917 psig V-2246 Less than or equal to 2846 psig V-2247 Less than or equal to 2774 psig V-2262 Less than or equal to 1133 psig
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( - -m Amendment No.
Page 3/4 7-14 DRAFT PLANT AND SAFE SHUT 00WN COOLING SUPPORT SYSTEMS JUN 131988 3/4.7.1 TURBINE CYCLE SAFETY VALVES - SHUTOOWN ,
/
LIMITING CONDITION FOR OPERATION
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3.7.1.6 a. At least one safety valve for each operating section af the steam generator shall be OPERABLE with its setpo,6t in accordance with Table 4.7..hl.*
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- b. The provisions of Specificit .:n ,3.0.4 are not applicable. > '
APPLICABILITY: SHUT 00WN and REFUELING ACTION: With ihss than the above required safety valves OPERABLE, restore the inoperable valve ;a OPERABLE status prior to reaching a CALCULATED BULK CORE TEMPERATURE of 760 degrees F or suspend all operations involving CORE ALTERATIONS or control rod movements resulting in positive reactivity changes.
SURVEILLANCE REQUIREMENTS 4.7.1.6 No additional surveillances reqd' ed oeyool tnose identified per Specification 4.7.1.5. e' !
Setpoint verification requires power '/evels not included in the Applicability of this Specification. Where tne test int.erval has oeen exceeded or tne sett'ing nas been affected by valve maintenance, valve settings snail oe estimated anc verifiec ce Soecification 3.7.1.5.
Amendment No.
Page 3/4 7-15 DRAFT BASIS SP?CIFICATIONS JUW 13 888 FOR .LC0 ' 3. 7.1. 5/SR 4.7.1.5 AND LCO 3.7.1.6/SR 4.7.1.6 -
The economizer-evaaorator-superheater (EES) section of eacn. steam S
s generator loop is Drotected by three spring-loaded safety valves, each with one-third nominal relieving capacity of each loop. The eheater section of each steam genarator loop is protected from overpressure transients by a single safety valve. These steam V generator safety valves a-e described in the FSAR, Section 10.2.5.3.
These steam generator safety valves are designed to relieve steam and can be damaged by rapid cyclic actuations tnat occur when they relieve water. T protect these valves, only one EES safety valve and the reheater safety valve are maintained in service ia each loop, through startuo evolutions with only one boiler feedwater pumo supplying feedwater' to tne EES sections. As additional boiler feedwater puaps' are placed in service, additional safety valves are also placed in service. The use of one safety valve per steam generator section during SHUT 00WN and REFUELING is acceptable, as it is capable of relieving the available flow. j Also, other power actuated valves .th.tt are capable of relieving pressure fron, the main steam and reheat piping are included in the FSV design.
The above valves are required to be tested in accordance with ASME Section XI, IGV requirements every 5 years (or less, depending on failures) or af ter maintenance. To satisfy tne testing criteria, the valves must ce tested with steam. Since tnese valves are permanently installed in steam piping, the approoriate .eans for testing requires the plant to be operating at steady state conditions, and close to the steam conditions expected at the set:oint. Power levels above 50*; RATED THERMAL POWER are suf ficient to acnieve this. Also, 7 days ensures setootnt verification witnin a reasonable time, noting that the test schedules are such that all "alves are not tested at the same time and tnus, s:ne valves will normally be OPERABLE.
During all MODES, witn one EES safety valve inoperable, plant operation is restricted to a condition for whicn the remaining safety valves nave sufficient relieving cacability to prevent overoressurization of any steam generator section. Conversely, with any reheater safety valve inocerable, olant coeration is restricted to a more restrictive MODE.
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A 72-hour action time for recair or SHUTOOWN cue to inocerable safety valves ensures tnat tnese valves are returnec to service in a relatively snort seriod of time, curing anich an overpressure transien* is unli(ely. 0:eration at :aer for 72 n0urs coes not result .n a significant loss of safety function for any extenced peried.
The setooints for tre safety valves 'centified in Table 4.7.1-1 are tnose values icentified in tne :5 4 .<itn tolerances applied such.that l tne Technical Scecifications l incorocrate anucercoundset-fint.
This is consistent with n:t incorcorating normal ocerating limits in tnese Scecifications.
Amendment No.
Page 6-8 MMT ADMINISTRATIVE CONTROLS Technical Advisors 6.2.3 The fun: tion, responsibilities and authority of the Technical Advisors shall be as follows:
Function 6.2.3.1 The Technical Advisors shall function to make objective evaluations of plant conditions and to advise or assist plant management in correcting conditions that may compromise safety of operations.
Responsibilities 6.2.3.2 The Technical Advisors are responsible for:
- a. Maximizing plant safety during and after accidents, transients, and emergencies by independently assessing plant conditions and by providinn technical assistance to mitigate anf nimize the effects of such incidents ans r(e recommendations to the Superintendant s f Operations,
- b. Reviewins abnormal and emergency procedures,
- c. Assisting the operations staff in applying the requirements of the Technical Specifications,
- d. Providing evaluation of Licensee Event Reports from other plants as assigned, and
- e. The Technical Advisor shall be in the control room within one hour after an emergency call. The Technical Advisors shall work on a normal day work schedule, but will be placed "on call" af ter normal working hours.
Authority 6.2.3.3 The Technical Advisors shall report to, and be directly responsible to, the Systems Engineering fia n ager . The Technical Advisors shall maintain independence from normal plant operations to be objective in their evaluations.
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Amendment No.
Page 6-10 DRAFT JUN 131988 ADMINISTRATIVE CONTROLS _.-
4 .
6.5 REVIEW AND AUDIT 6.5.1 Plant Operations Review Committee (PORC).
Function 6.5.1.1 The PORC shall function to advise the Manager of '.uclear Production on all matters related to nuclear safety.
Composition 6.5.1.2 The PORC shall be composed of the following:
Chairman: Station Manager Nuclear Support Manager Superintendent of Chemistry and Radiation Protection (Radiation Protection Manager)
Operations Manager Maintenance Department Manager Systems Engineering Manager Nuclear Training Manager Health Physics Supervisor Superintendent of I & C Maintenance Superintendent of Operations Alternates 6.5.1.3 An alternate chairman and alternate members, if required, shall be appointed in writing by the PORC Chairman to serve in the absence of a chairman or a member; however, no more than two alternate members shall participate as voting members in PORC activities at any one time.
Meeting Frecuency 6.5.1.4 The PORC shall meet at least once per calendar month and as convened by the Chairman or his designated alternate.
Quorum 6.5.1.5 A quorum shall consist of the Chairman or alternate Chairman, and four members including alternates.
p u Attachment 3 e to P-88205 L
INCORPORATION OF RECENT TECHNICAL SPECIFICATION AMENDMENTS INTO TSUP
'This Attachment is -a re-submittal of several discussions provided previously in-Attachment 2 to_P-88082. The impact of Amendment 51 on the Upgraded -FSV Technical Specifications has been re-evaluated in several areas, as shown herein.
Amendment No: 51 Current Technical Specification: SR 5.2 21
Description:
Testing of valves and transfer switches that must be manually positioned for- actuation of the ACM mode of operation.
'TSUP Impact: None. Consistent with the philosophy ano 'evels of detail provided in TSUP,_ these valves and instruments are not explicitly addressed in the Specifications, but they hre covered. The
. operability of the ACM transfer switches is demonstrated during ACM load testing per TSUP SR 4.8.4.e.2. , Also, the operability of the valves is assured by other TSUP surveillances for their associated systems.
Amendment No: 51 Curren' Technical Specification: SR 5.2.24 9
Description:
Functicnally test each purification cooling water pump and controls, monthly. Annually verify performance and calibrate instrumentation.
TSUP Impa t: The surveillance of these pumps was added to the revised final draft of SR 4.7.5.b and c. These pumps supply cooling water t6 the helium purification coolers, which are included in the depressurization flow path (addressed in TSUP Specification 3/4.7.5). There are other means of supplying these coolers, such as the PCRV liner cooling system or nitrogen recondensing chilled water. These pumps are used in the event of a leak in a helium purification cooler, to provide cooling without spreading activity to other systems.
Instrumentation and control; are addressed via PSC's administrative controls.
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Attachment 3 to P-88205 Amendment No: 51 Current Technical Specification: SR 5.2.24.h
Description:
Test valves used for automatic isolation of purification cooling water system and reactor plant cooling water system.
TSUP Impact: Requirements for these valves have been added to the revised final draft of Specification 3/4.6.4.3.