Text

Proposed Tech Specs Consisting of Supplemental Info to Proposed Amend 147,Rev 2 Re Diesel Generator Outages
	ML20235F530
Person / Time
Site:	Rancho Seco
Issue date:	09/22/1987
From:	; SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:	;
Shared Package
ML20235F529	List: ML20235F525; ML20235F530;
References
	TAC-63030, NUDOCS 8709290185
	Download: ML20235F530 (127)
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TECHNICAL SPECIFICATION CHANGE LOG NO. 0760, rev. 3 ATTACHMENT 1 -- DIESEL GENERATOR OUTAGES Proposed Amendment 147, rev. 2, supplement 1 Page 1 of 12 3.28.2 If one essential ventilation system train for the control room in the TDI Diesel Generator Building is non-OPERABLE, demonstrate the operability of the remaining train. Restore the non-OPERABLE train to OPERABLE status within I days or be in at least HOT SHUTDOWN within six hours and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

3.1.1.7 The pressurizer shall be OPERABLE, except when the reactor is in COLD SHUTDOWN, with 3 groups of heaters in two separate banks that are capable of being powered by the diesel generator trains. With the heaters in one bank non-OPERABLE, either I restore the bank to OPERABLE status within 3 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . With the heaters in both banks non-OPERABLE, either restore one bank to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Bases-3.1:

There are 3 groups of heaters in bank 2, and 3 groups of heaters in bank 3 that are capable of being powered by the diesel generator. Each set of the 3 groups of heaters has a nominal rating of 126 kW which provides assurance that these heaters can be energized during a loss of off-site power condition to maintain natural circulation at HOT SHUTDOWN.

Di scussi on: l The above LCOs match the corresponding standard technical specifications. The only change in these paragraphs with respect i to reviuion 2 is the change from the 15 day LCO to 3 days.

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l-h TECHNICAL' SPECIFICATION CHANGE LOG NO. 0760, rev. 3 ATTACHMENT 1 -- DIESEL GENERATOR OUTAGES Proposed Amendment 147, rev. 2, supplement 1 Page 2 of 12 I Prooosed Amendment 147. revision 2 3.7.2.B. Both diesel generator trains shall be operable except should one diesel generator train become inoperable the operability of at least two 220 KV lines circuits shall be demonstrated by performing surveillance requirement 4.6.1.A within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months thereafter and surveillance requirement 4.6.3.A.4 is performed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and at least once per 7 days thereafter. If the diesel generator train is not restored to operable status within 15 days, the reactor shall be in hot shutdown within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in cold shutdown within the f ollowing 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

Pronosed Amendment 147. revision 2. sucolement 1 3.7.2.B.1 Both diesel generator trains shall be OPERABLE prior to leaving COLD SHUTDOWN conditions.

3.7.2.B.2 Should any single diesel generator (GEA, or GEB, or GEA2, or GEB2) become non-OPERABLE due to any cause other than preplanned preventive maintenance or testing, then complete all of the following actions:

a. within i hour the operability of at least two 220 KV lines circuits shall be demonstrated by obtaining acceptable results from perf orming surveillance requirement 4.6.1.A Ci.e., breaker alignment and power availability 3; and at least ;

once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter; or the reactor shall '

be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in !

COLD SHUTDOWN within the f ollowing 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ,

b. within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months obtain acceptable results from performing surveillance requirement 4.6.3.A.4 C1.e., manual diesel start]; and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter; or the reactor shall be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . ;

c. If the non-OPERABLE diesel generator is not restored to OPERABLE status within 3 days, i.e.,

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , from when the non-OPERABLE condition was established, the reactor shall be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN '

within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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. TECHNICAL-SPECIFICATION CHANGE. LOG NO. 0760, rev. 3.

ATTACHMENT 1 -- DIESEL, GENERATOR OUTAGES-

' Proposed Amendment.147, rev. 2, supplement 1 Page.3 of 12 3.7.2.B.3 Should diesel. generators GEA2'and GEB2 become non-OPERABLE due to'any cause other than preplanned preventive maintenance or testing, then complete all of the f ollowing actions:

a. within i hour the operability of at least two 220 KV lines circuits shallibe demonstrated by obtaining acceptable results from performing surveillance requirement 4.6.1.A; and at least once per-8 hours thereafter; or the reactor shall be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b. If both GEA2 and GEB2 diesel generator are non-i OPERABLE 4 [RE: Technical Specification 3.4.2.33 hours3.819444e-4 days 0.00917 hours 5.456349e-5 weeks 1.25565e-5 months after the second inoperability, the reactor shall be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

c. If one diesel generator (GEA2 or GEB2) is returned to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , follow i the 3.7.2.B.2.c 3 day, i.e., 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , LCD which l

commenced at the time the remaining non-OPERABLE condition was established.

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TECHNICAL SPECIFICATION CHANGE LOG NO. 0760, rev. 3 ATTACHMENT 1 -- DIESEL GENERATOR OUTAGES Proposed Amendment 147, rev. 2, supplement 1 Page 4 of 12 Proposed Amendment 147. revision 2 3.7.2.E. Both diesel generator trains shall be operable except should both trains be inoperable the operability of at least two 220 KV lines shall be demonstrated by performing surveillance requirement 4.6.1.A within i hour and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter. If one diesel generator train is not restored to operable status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , the reactor shall be in hot shutdown within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in cold shutdown within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . With one diesel generator train restored to operable status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , follow 3.7.2.B.

Proposed Amendment 147. revision 2. sucol emen t 1 3.7.2.E.1 Should the following diesel generators combinations (GEA/GEA2, or GEB/GEB2) become non-OPERABLE due to any cause other than preplanned preventive maintenance or testing, then complete all of the following actions

a. within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months the operability of at least two 220 KV lines circuits shall be demonstrated by obtaining acceptable results from performing surveillance requirement 4.6.1.A; and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter; or the reactor shall be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b. within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months obtain acceptable results from performing surveillance requirement 4.6.3.A.43 and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter; or the reactor shall be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ,

c. If GEA/GEA2, or GEB/GEB2 combinations are non-OPERABLE 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after the second inoperability, the reactor shall be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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i TECHNICAL SPECIFICATION CHANGE LOG NO. 0760, rev. 3

-ATTACHMENT 1 -- DIESEL GENERATOR OUTAGES Proposed Amendment 147, rev. 2, supplement 1 Page 5 of 12

d. If one non-OPERABLE diesel generator in the GEA/GEA2, or GEB/GEB2, combination is returned to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , follow the 3.7.2.B.2.c 3 day, i.e., 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , LCO which commenced at the time the the remaining non-OPERABLE condition was established.

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TECHNICAL SPECIFICATION CHANGE LOG NO. 0760, rev. 3 ATTACHMENT 1 -- DIESEL GENERATOR OUTAGES Proposed. Amendment 147, rev. 2, supplement 1 Page 6 of 12 3.7.2.E.2 Should the diesel generator pairs GEA/GEB, or GEA/GEB2, or GEB/GEA2 become'non-OPERABLE due to any cause other than preplanned preventive maintenance or testing, then complete all of the following actions:

a. If GEA/GEB, or GEA/GEB2, or GEB/GEA2 diesel generators are non-OPERABLE 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after the second inoperability, the reactor shall be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b. If one non-OPERABLE diesel generator in the GEA/GEB, or GEA/GEB2, or GEB/GEA2 non-OPERABLE pair is returned to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , follow the 3.7.2.B.2.c 3 day, i.e., 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , LCO which commenced at the time the remaining non-OPERABLE condition was established.

ERE: the two hour LCO is consistent with f Regulatory Guide 1.93, December 19743 l

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1 p . TECHNICAL SPECIFICATION CHANGE' LOG NO. 0760, rev. 3 ATTACHMENT 1 -- DIESEL GENERATOR OUTAGES Proposed Amendment 147, rev. 2, supplement 1 Page 7 of 12 1

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Discussion:

This change incorporates the recommendations of IE Information 1 Notice 84-69, Supplement I, " Operation of Emergency Diesel y Generators." It' eliminates the 15 day period, where the operable '

diesel'is run. continuously with minimum load. Running the diesel withiminimum load may reduce its operability. The surveillance requirements are revised to reduce the number of starts and more clearly define'the operability of off-site sources to be consistent with the recommendations of Generic Letter 84-15.

A single diesel generator inoperability is covered by 3.7.2.B.2.

Inoperability of GEA2 and~GEB2 at the same time is covered by l:

3.'7. 2. B. 3.

Inoperability of a " train" of diesel generators (i .e. , GEA/GEA2 and GEB/GEB2) is covered by 3.7.2.E.1.

Inoperability of both diesel generators in the combinations LGEA/GEB, GEA/GEB2, and GEB/GEA2 is covered by 3.7.2.E.2. ]

Generic Letter G4-15 states that the maximum time that an-individual diesel oenerator may be non-OPERABLE shall be established bv the licensee based on the manufacturer's recommendations and previous maintenance and repair experience.

The District has fifteen years of operating experience with the two Bruce /GM diesel generators. The techniques of maintenance and repair are well established and documented. Some of the more common problems with the engines ares turbocharger failure and power pack failures (i . e. , involving a piston, cylinder liner, or f connection rod). Part availability is not always a limiting feature of a repair project. To repair a turbocharger is <

normally a three day exercise. A power pack failure would i normally b- a one week failure depending on the severity of the d specific event. j i

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ll l TECHNICAL SPECIFICATION CHANGE LOG NO. 0760, rev. 3 l ATTACHMENT 1 -- DIESEL GENERATOR OUTAGES l Proposed Amendment 147, rev. 2, supplement 1 Page 8 of 12 Experience at Rancho Seco indicates that most diesel generator '

corrective maintenance work has taken approximately one-week.

One repair during power operations exceeded 15 days and. required i the low-load operation of the second diesel generator. Beginning with Proposed Amendment 147, a single inoperability of either Bruce /GM diesel engine will initiate a 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months LCO, significantly more conservative than t'a current 30 day LCO allowed in existing technical sp eci f i c a'..i on s. The regular and high level of maintenance attention to all diesel generators at Rancho Seco provides confidence that more than one will not become non-OPERABLE coincidentally. Even so, proposed technical specifications provide specific times to repair diesel generators depending on which one(s) is(are) non-OPERABLE.

Standard Technical Specifications for diesel generator operability are written for a plant with a two diesel generator configuration. For the Rancho Seco four diesel generator configuration, a single non-OPERABLE diesel generator impacts 3 plant safety to varying degrees as a function of which diesel is '

non-OPERABLE.

Proposed Amendment 147 is written to treat the electrical system.

as two trains with one source of emergency power for each train.

Proposed Amendment 147 institutes LCOs for diesel generator inoperability/ repair as if there were only one diesel engine / generator for each 4160V safety bus, i.e., both diesel generators for Train A need not be non-OPERABLE to initiate an LCO time clock. However, during the LCO, several other diesel generator combinations can physically fulfill the safety functions required to mitigate an accident. Therefore, an extra level of safety is provided in the Rancho Seco design.

The system grid that supplies Rancho Seco includes several reliability features that minimize the probability of loss-of-off-site power due to faults in network interconnections and associated switching.

Five transmission lines connect the Rancho Seco Generating Station switchyard to switchyards in the area transmission network. The area transmi ssion system can supply all area generation to load centers with any one line out-of-service. The District performed an analysis (RE: USAR B.2.1.2) on the system stability to assure that the system will accommodate the trip of the Rancho Seco unit anti should such a trip occur, it will not disrupt availability of off-site power.

TECHNICAL' SPECIFICATION CHANGE LOG NO. 0760, rev. 3 ATTACHMENT.1.-- DIESEL GENERATOR OUTAGES Proposed Amendment 147, rev. 2, supplement 1 Page.9 of 12 t

The transmission lines from the station switchyard follow two different right-of-ways. Two of,the lines are routed south and the.other three are routed-to the west.

The arrangement in the switching station includes two full capacity main buses. Primary and backup relaying are provided for each circuit along with circuit breaker failure backup protection. These provisions permit the f ollowings j o 'Any circuit can be switched under normal or fault conditions without affecting any other circuit o Any single circuit breaker can be isolated for maintenance without interrupting the power to any ,

circuit or defeating the protection to any circuit j l

o A short circuited single main bus can be isolated .I without interrupting service to any circuit. -

o . Backup relaying provides separation in the event of primary relaying failing to trip. -l The primary bushing taps of the main and start-up transformers

. include three-phase, 230kV no-load disconnect switches. These disconnects permit isolation of these transformers to allow reclosing connecting loops between the east and the west 230kV buses. (RE: USAR B.2.1.2)

Because of the service perforced by the TDI diesel generators and the normal and emergency power configuration at Rancho Seco, each TDI diesel will have a 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months LCO for repair, based on the LCO for AFW in-Technical Specification 3.4.2.2.

There are four independent bus unload / loading sequencers, one for each safety bus. Under-voltage would need to be sensed on each saf ety bus f or all f our diesels to activate and carry electrical load.

From an overall perspective, ECCS loads are carried on GEA and GEB. GEA2 and GEB2 carry auxiliary feedwater pump motors, essential HVAC, and pressurizer heaters.

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I f- TECHNICAL SPECIFICATION CHANGE LOG NO. 0760, rev. 3 ATTACHMENT i -- DIESEL GENERATOR OUTAGES Proposed Amendment 147, rev. 2, supplement i Page 10 of 12 l

I l The District performed a system interaction study performed for {

l the four diesel generator sets. It demonstrated that GEA did not interact with GEA2. Correspondingly, GEB did not interact with 4 GEB2. The two safety trains are separate. Therefore, the f our diesels are in ef f ect separate entiti es. However, the routing of cables for train A are routed together, without regard to whether the current source is 4A or 4A2 bus. A cable problem resulting in non-operable buses are covered by Proposed Amendment 147, item ;

I 3.7.2.H with more restrictive LCOs.

For the scenario where only GEA and GEB are operable, two design basis accidents are involved. Note, in both cases, batteries supply the 120V vital buses. First, consider an accident requiring ECCS loads with a single GEA or GEB failure, and off-site power available. In this situation, safety systems needed to bring the plant to hot shutdown would control the accident using off-site power sources along with one GEA or GEB in standby.

The second possible accident requires ECCS loads with a single GEA or GEB failure, and a concurrent loss of off-site power. In this eventuality, AFW will be f unctional using the steam turbine driven pump. Essential HVAC and pressurizer heaters will not work. During a LOCA, credit for the pressurizer is not taken.

Operations personnel can take protective action to guard against radiation exposure if Control Room radiation levels become excessive. The remaining operable and loaded GEA or GEB will be able to provide suf ficient power to supply one ECCS train. These conditions will permit the plant to achieve hot shutdown.

The four diesel generator configuration at Rancho Seco can physically allow initiation of the designed safety functions using the f ollowing diesel / bus configurations, remembering that critical instrumentation and control (including EFIC) is battery backed:

combinations that are OPERATIONAL GEA/GEA2 -- allowed for 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months by technical specifications GEA/GED -- allowed for 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by technical specifications ,

GEA/GEB2 -- allowed for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months by technical specifications GEB/GEB2 -- allowed for 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months by technical specifications .

GEB/GEA2 -- allowed f or 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months by technical specifications j The Rancho Seco design provides a margin of saf ety not available in a conventional two diesel configuration.

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TECHNICAL SPECIFICATION CHANGE LOG NO. 0760, rev. 3 ATTACHMENT 1 -- DIESEL GENERATOR OUTAGES-Proposed Amendment 147, rev. 2, supplement i Page 11 of 12 i

Each 4160V bus is independent of the existing bus in the same train but not redundant. Loss of a 4160V bus results in an incomplete train, and therfore, from the standpoint of redundancy, must be considered as the loss of the complete train.

(RE: ECN A-3660, DBR revision 6, bottom of page 3)

Excluding the presence of the diverse feeds into the Rancho Seco {

switchyard, the following is the only configuration.that cannot 5 support the initiation of all the required safety functions: I GEA2/GEB2 -- allowed for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months by technical specifications Therefore, should one Bruce /GM diesel be non-OPERABLE, and the second Bruce /GM experience single failure, the ECCS safety function could not be met using only TDI diesel generators during a loss-of-off-site-power. However, consider that the current technical specifications (which do not assume the presence of the {

TDIs) allow up to 30 days to repair one of two non-OPERABLE diesel generators. The two hour LCO for the condition of non-OPERABLE GEA/GEB, or GEA/GEB2, or GEB/GEA2 is consistent with i Regulatory Guide 1.93, December 1974. !

A single non-OPERABLE TDI diesel generator does not impact the completion of ECCS functions. In addition, the redundant auxiliary feedwater pump is available on the other train.

Auxiliary Feedwater operability is covered under 3.4.2.2 and 3.4.2.3. The normal reliable sources of power from off-site are supplying the non-OPERABLE diesel 's bus so that both auxiliary feedwater pumps are available. Lastly, one auxiliary feedwater pump is equipped with a steam turbine driver supplied by the plant main steam lines which will permit auxiliary feedwater pump operation without electric power for the motor drivers < Even f under the hypothetical loss-of-off-site power, combined with a main steam line break and single TDI failureg one auxiliary feedwater pump would still be available to provide steam l generator cooling under the control of EFIC.

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The time permitted to repair a cingle TDI diesel inoperability will be 3 days, i.e., 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; less than thirty days currently allowed in the existing technical specification for the older Bruce /GM diesel generators. Considering the other applicable technical specifications and the definition of OPERABLE, plant -

operations will be limited by other technical specifications. .

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l TECHNICAL SPECIFICATION CHANGE LOG NO. 0760, rev. 3 ATTACHMENT 1 -- DIESEL GENERATOR OUTAGES Proposed Amendment 147, rev. 2, supplement 1 Page 12 of 12 The time permitted to repair two non-OPERABLE TDI diesel generators will be 4 Ematching existing Technical Specification 3.4.2.33 hours3.819444e-4 days 0.00917 hours 5.456349e-5 weeks 1.25565e-5 months because the diesels needed to support ECCS loads are still <

OPERABLE; reliable off-site power is still available, and; one j auxiliary feedwater pump can be run using the dedicated steam turbine.

Generic Letter 84-15 states that every reasonable effort shall be i made to restore individual diesel oenerators to OPERABLE status within that time period. Every reasonable effort shall be interpreted to mean that disonosis and repairs are to beoin immediately and are to continue uninterrupted until the diesel oenerator is declared OPERABLE or an orderly retreat to COLD SHUTDOWN is ini tiated.

This change incorporates the recommendations of IE Information Notice 84-69, Supplement I, " Operation of Emergency Diesel Generators." It eliminates the 15 day period where the OPERABLE diesel is run continuously with minimum load-because running the diesel with minimum load may reduce its reliability. The surveillance requirements are revised to reduce the number of starts and more clearly define the operability of off-site sources to be consistent with the recommendations of Generic Letter 84-15.

TECHNICAL SPECIFICATION CHANGE LOG NO. 0760, rev. 3 ATTACHMENT 2 -- NUCLEAR SERVICE BUS OUTAGES l Proposed Amendment 147, rev. 2, supplement 1 Page 1 of 2 Proposed Amendment 147. revision 2 3.7.2 H. Nuclear service buses as listed in 3.7.1.D and 3.7.1.E shall be operable except should one nuclear service bus become inoperable for greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , the reactor shall be in hot shutdown within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in cold shutdown within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . If more than one nuclear service bus as listed in 3.7.1.D and 3.7.1.E should become inoperable, within one hour take action to place the reactor in hot shutdown within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in cold shutdown within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

I Proposed Amendment 147. revision 2. sucolement 1 Specification 3.7.2.H. Nuclear service buses as listed in 3.7.1.D and 3.7.1.E shall be OPERABLE.

APPLICABILITY:

I Startup through Power Operations ACTION: l Should one nuclear service bus become non-OPERABLE for greater ,

than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , 1 i

a) the reactor shall be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months i and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . I If more than one nuclear service bus from more than one train as j listed in 3.7.1.D and 3.7.1.E should become non-OPERABLE, l l

b) within one hour take action to place the reactor in HOT {

SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . I i

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I This supplement clarifies that only multiple nuclear service bus j inoperabilities in more than one train cause a one-hour LCO for j reactor shutdown, j l

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p O TECHNICAL' SPECIFICATION CHANGE LOG NO. 0760, rev. 3 ATTACHMENT 2 -- NUCLEAR SERVICE BUS OUTAGES.

Proposed. Amendment 147, rev. 2, supplement 1; Page 2 of 2 The revision to' proposed Technical Specification 3.7.2.H _l clarifies. the relative importance of ' bus inoperabilities. in one f train versus bus inoperabilities in two trains. The previous intent is clear. Actions to place-the reactor in HOT SHUTDOWN within one-hour as a result of, for example, two nuclear service buses in train A inoperable, is not a desirable action because it requires a; rapid power down. A single bus inoperability only requires a HOT. SHUTDOWN after twenty-four hours of inoperability.

So long as additional ~inoperabilities are in the same train, the same LCD will apply. (RE: Robert Cool-and Steven Miller on September 4,' 1987)

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c TECHNICAL SPECIFICATION CHANGE LOG NO. 0760, rev. 3 ATTACHMENT 3 -- FIRE PROTECTION

' Proposed Amendment 147, rev. 2, supplement-1 Page 1 of 2

'Eristino Specification.

N/A New Specification Table 3.14-1 FIRE DETECTION INSTRUMENTS FOR SAFETY SYSTEMS Minimus OPERABLE Zone Instrument Location Heat Flaae Sacke 105 Diesel Generator Building 2 3 2 106 Diesel Generator Building 2 3 2 (RE: Log No. 1019 ECN R-0767, rev. 13 DBR, rev. 2) 3.14.3.1.a. Diesel Generator Building (Zone 105)

.n. Diesel Generator Building (Zone 106)

Table 3.14-2 INSIDE BUILDING FIRE HOSE STATIONS ID No. Location

!!! Diesel Benerator Building Hose Stations FPHS-D-001 Train A Engine Room Elevation O' FPHS-D-002 Train A Control Roos Elevation O' FPHS-D-003 Train A Nezzanine Elevation 10'6" FPHS-D-004 Train B Engine Room Elevation O' FPHS-D-005 Train B Control Room Elevation O' FPHS-D-006 Train B Mezzanine Elevation 18'6"

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l TECHNICAL SPECIFICATION CHANGE LOG NO. 0760, rev. 3 ATTACHMENT 3 -- FIRE PROTECTION Proposed Amendment 147, rev. 2, supplement 1 Page 2 of 2 l Di scussi on:

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These changes add the fire detection instruments, the sprinkler systems,'and the fire hose stations in the new diesel generator building. These are additions to the d specifications that provide fire protection features for portions of redundant systems important to safe shutdown as ,

described in the Rancho Seco Fire Hazard Analysis Report. .

Subsequent to Proposed Amendment 147, revision 2, a design ,

change was made to the TDI Diesel Generator Building fire l protection system That change brought the fire protection )

system of the TDI Diesel Generator Building into compliance I with applicable National Fire Protection Association (NFPA)

Codes. The smoke and flame detectors on the mezzanine are replaced by detectors capable of withstanding the maximum 1 design operating temperature of 140 F. (RE: Log No. 1019; f

ECN R-0767, rev. 1; DBR, rev. 2) i 1

TECHNICAL SPECIFICATION CHANGE LOG NO. 0760, rev. 3 ATTACHMENT-4 -- ELECTRICAL PROTECTION Proposed-Amendment 147, rev. 2, supplement 1 Page 1 of 2 Existina Specification Table 4.1-1 INSTRUMENT-SURVEILLANCE REQUIREMENTS Channel Description Check Test ~ Calibrate Remarks.

57. Voltage Protection S(1) (1)-Compare voltmeter readings

a. Under-voltage M R

b. Over-voltage M R

c. Time Delay M R New Specification

57. Voltage Protection 7

a. Under-voltage M (1) N/A R (1) Test using

. Relay-Setpoint undervolt-

b. Under-voltoge M (1) N/A R age. relay's Relay Time Delay " TRIP TEST."

No quanti-tative measurements Discussions Proposed Amendment 147 deletes the MONTHLY surveillance requirement associated with the over-voltage relay deleted by ECN 3-1045.

The " check each shift requirement" ie deleted because if the voltmeters are out of the calibrated range or the voltmeter

" window" moves away from the actual voltage, one of two things will happens o The under-voltage relays would operate.

o IDADS alarm (E1502, E1503, E1504, E1505) would alarm in l_ the Control Room. The IDADS alarms are checked by 1 surveillance procedures.

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TECHNICAL SPECIFICATION CHANGE LOG.NO. 0760, rev. 3 ATTACHMENT 4=-- ELECTRICAL PROTECTION Proposed. Amendment 147, rev. 2, supplement 1 Page 2 of 2-1

.The surveillance procedure for the-under-voltage relays, per the. note in thefproposed' technical specification, does not quantitatively measure or test the f unctions. The monthly surveillance only verifies operability. The setpoint'and

' time delay-are not quantitatively measured monthly. It-is therefore, more accurate ~to say that the. surveillance procedure is a1" check." The' frequency of'" MONTHLY" was

{ retainedLfrom the original. A MONTHLY' test is not required for the under-voltage relay circuit because of mean-time to failure considerations and the fact that the relay fails to the trip. condition.-

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. The response time on the time delay function is acknowledged .

i to exist qualitatively by the data taker during the surveillance' test.

The revision to this technical specification reflects an improvement-in the understanding of the system and supersedes the previous proposed amendment for this item.

(RE: Ed Stockman,. 7/29/97, 9:00 AM) l

'(RE: Denis Jones, 9/4/07, 11:10 AM)-

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l l TECHNICAL SPECIFICATION CHANGE LOG NO. 0760, rev. 3 l

ATTACHMENT 5 -- FUEL OIL SAMPLING Proposed Amendment 147, rev. 2, supplement 1 Page 1 of 4 l

l Proposed Amendment 147. revision 2 l

4.6.3 Each diesel generator shall be demonstrated OPERABLE by verifying that both diesel generators in the train are OPERABLE (A and A2, B and B2). Each diesel generator shall be demonstrated OPERABLE.

4.6.3.B Fuel Oil Storage

1. By removing accumulated waters a) From the day tank at least monthly after each occasion when the diesel is operated for greater than i hour, and b) From the storage tank at least monthly.

2. By sampling new fuel oil in accordance with ASTM D4057-81 prior to addition to the storage tanks and:

a) By verif ying in accordance with the tests specified in ASTM D270-65 (1975) prior to addition to the storage tanks that the sample has:

i) An absolute specific gravity at 60/60 F of greater than or equal to 0.83 but less than or equal to 0.90 or an API gravity at 60 F of greater than or equal to 26 degrees but less than or equal to 38 degrees in accordance with ASTM D1298-77.

ii) A kinte.atic viscosity at 40 C of greater than or equal to 1.9 centistokes, but less than or equal to 4.1 centistokes, or Saybolt, SUS at 100 F greater than or equal to 32.6, but less than or equal to 40.1. i iii) A flash point equal to or greater than 125 F, and iv) Water and sediment of less than or equal to 0.05 percent by volume per ASTM 1796-68.

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t TECHNICAL SPECIFICATION CHANGE LOG NO. 0760, rev. 3 ATTACHMENT 1 --

FUEL OIL SAMPLING Proposed Amendment 147, rev. 2, supplement 1 Page 2 of 4 b) By verifying within 31 days of obtaining the !

sample that the other properties specified in Table 1 of ASTM D975-81 are met when tested in ;

accordance with ASTM D975-81 except that the analysis for sulfur may be performed in accordance-with ASTM D1552-79 or ASTM D2622-82 (Note 2).

3. At least monthly by obtaining a sample of fuel oil from the storage tanks in accordance with ASTM D2276-73 (1978), and verifying that total particulate contamination is less than 10mg/ liter when checked in accordance with ASTM D2276-73 (1978), Method A.

Note 2: If one or more property is out of spec., verify within an additional 31 days that.a sample of fuel oil from the fuel oil storage i s within specification or replace the fuel oil within additional 15 days.

Proposed Amendment 147. revision 2. sunolement 1 4.6.3 Each diesel generator train shall be demonstrated OPERABLE by verifying that both diesel generators in the train are OPERABLE (A and A2, B and B2). Each diesel generator shall be demonstrated OPERABLE:

B. Fuel Oil Storage

2. By sampling new fuel oil in accordance with ASTM D4057-81 (1981) prior to addition to the storage tanks and a) ii) A Kinematic Viscosity at 40 of greater than or equal to 1.9 centistokes, but less than or equal to 4.1 centistokes; or Saybolt {

Viscosity (SUS at 100 F) .

of greater than or equal to 32.6, but less than or equal to 40.1 measured in accordance with ASTM D-88-81.

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TECHNICAL SPECIFICATION CHANGE LOG NO. 0760, rev. 3 ATTACHMENT 5 -- FUEL DIL SAMPLING Proposed Amendment 147, rev. 2, supplement 1 Page 3 of 4 b) By verifying within 31 days of obtaining the sample that the other properties specified in Table 1 of ASTM D975-81 are met when tested in accordance with ASTM D975-81, except that the analysis for sulfur may be performed in accordance with ASTM D1552-79 or ASTM D2622-82. (Note 2)

Note 2 If one or more properties are out of specification, within 62 days of obtaining the bad fuel oil, verify that an additional sample of fuel oil from the fuel oil j storage tank is within specification, er empty and '

refill the tank with a new shipment of fuel oil within 77 days of the original out-of-specification sample.

3. At least MONTHLY by obtaining a sample of fuel oil from the storage tanks in accordance with ASTM D4057-01 (1981), and verifying that total particulate contamination is less than 10 mg/ liter when checked in accordance with ASTM D2276-73 (1978), Method A.

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TECHNICAL SPECIFICATION CHANGE LOG NO. 0760, rev. 3 ATTACHMENT 5 -- FUEL OIL SAMPLING Proposed Amendment 147, rev. 2, supplement 1 Page 4 of 4

____________________ i j- Discussion:

Most of these requirements are presently being performed by plant surveillance procedures even though the items were not in the specifications. The additional requirements are based on latest NRC guidance. It ensures that new fuel is not contaminated prior to dumping into the fuel oil storage tank. Also the removal of accumulated water will ensure the fuel oil does not become contaminated during the storage period.

RE: Roy Yoshida (x4690) and George Cambell comments on ASTM standards to use for fuel oil sampling circa February 19, 1987. {

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RE: Wayne Hampton note concerning the purchase of a Saybolt Viscosimeter from the Koehler Instrument Company for the analysis of diesel fuel oils by the Chemistry Department. ASTM 975-81 does not refer to ASTM D-88-81. ASTM D-88-81 recommends D-445 and D-2170 as preferable methods for the determination of kinematic viscosity. Item 2.a.fi provides the exception to allow the use of the Chemistry Department equipment. 4 Standard technical specifications call for sampling fuel oil in accordance with ASTM D-270-65 and analyzing the sample using table 1 in ASTM D-975-74 for viscosity, water and sediment. The standard technical specification conforms with Regulatory Guide 1.137, revision 1, which endorses ANGI N195-1976 as supplemented by ASTM D975-77. A more recent edition, ASTM 975-81, specifically references the use of ASTM D-4057 as the sampling method, replacing D-270-65 (1975).

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PROPOSED AMENDMENT 147 REVISION 2 SUPPLEMENT 1 ATTACHMENT 6 ACTUAL PAGE CHANGES 1

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS

.c TABLE OF CONTENTS (Continued)

Section' Eagg 3.14.5 .C Fire Hose Stations 3-57 3.14.6 Fire Barrier Penetration Fire Seals 3-58 3.15 RADI0 ACTIVE LIOUID EFFLUENT INSTRUMENTATION 3-60 3 16

. RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 3-63 3.17 LIOUID EFFLUENTS 3-70 3.17.1 Concentration- 3-70 3.17.2 D01g 3-71 3.17.3 Liauid Holduo Tanks 3-72 3.18 GASEOUS EFFLUENTS 3-73 3.18.1 Dose Rate 3-73 3.18.2 Noble Gases 3-74 3.18.3 Iodine-131. Tritium and Ra'dionuclides in Particulate Form 3-75 3.19 GASEOUS RADHASTE TREATMENT 3-78 3.20 GAS STORAGE TANKS 3-79 3.21 SOLID RADI0 ACTIVE WASTES 3-80 3.22 RADIOLOGICAL ENVIRONMENTAL MONITORING 3-81 3.23 LAND USE CENSUS 3-87 3.24 EXPLOSIVE GAS MIXTURE 3-89 3.25 FUEL CYCLE DOSE 3-90 3.26' INTERLABORATORY COMPARISON PROGRAM 3-92 147- 3.27- N11 CLEAR SERVICE ELECTRICAL BUILDING EMERGENCY HEATING 3-93 AND AIR CONDITIONING 3.28 TDI DIESEL GENERATOR CONTROL ROOM ESSENTIAL 3-94 YEEIJ.LATION SYSTEM Proposed Amendment No. 147 iv t

1 RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS TABLE OF CONTENTS (Continued)

Section Eage 4.26 RADIOLOGICAL ENVIRONMENTAL MONITORING 4-83 4.27 LAND USE CENSUS 4-86 4.28 EXPLOSIVE GAS MIXTURE 4-87 4.29 FUEL CYCLE DOSE 4-89 4.30 INTERLABORATORY COMPARISON PROGRAM SURVEILLANCE REQUIREMENT 4-90 4.31 NUCLEAR SERVICE ELECTRICAL BUILDING EMERGENCY HEATING 4-91 VENTILATION AND AIR CONDITIONING 147- 4.32 TDI DIESEL GENERATOR CONTROL ROOM ESSENTIAL 4-92

- VENTILATION SYSTEM 5 DESIGN FEATURES 5-1 5.1 SJlE 5-1 5.2 CONTAINMENT 5-2 5.2.1 Reactor Buildino 5-2 5.2.2 Beactor Buildina Isolation System 5-3 5.3 REACTOR 5-4 .

5.3.1 Reactor Core 5-4 5.3.2 Reactor Coolant System 5-4 5.4 NEH AND SPENT FUEL STORAGE FACILITIES 5-6 5.4.1 New Fuel Insoection and Temocrary Storage Rack 5-6 5.4.2 New and Soent Fuel Stora.ge Racks and Failed 5-6 Fuel Storaae Container Rack 4 5.4.3 New and Soent Fuel Temocrary Storaan 5-6 5.4.4 Soent Fuel Pool and Storaae Rack Desian 5-6 i

Proposed Amendment No. 147 ;

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS LIST OF TABLES Iahlg Page 2.3-1 REACTOR PROTECTION SYSTEM TRIP SETTING LIMITS. 2-9 3.5.1-1 INSTRUMENTS OPERATING CONDITIONS 3-27 3.5.5-1 ACCIDENT MONITORING INSTRUMENTATION OPERABILITY REQUIREMENTS 3-38b 3.6-1 SAFETY FEATURES CONTAINMENT ISOLATION VALVES 3-40 3.7-1 VOLTAGE PROTECTION SYSTEM RELAY TRIP VALUES 3-41a 3.7-2. VOLTAGE PROTECTION SYSTEM LIMITING CONDITIONS 3-41b 3.12-1 SAFETY RELATED HYDRAULIC SNUBBERS 3-51a-e 3.14-1 FIRE DETECTION INSTRUMENTS FOR SAFETY SYSTEMS 3-55 3.14-2 INSIDE BUILDING FIRE HOSE STATIONS 3-57a 3.15-1 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 3-61 3.16-1 RADI0 ACTIVE GASES EFFLUENT MONITORING INSTRUMENTATION 3-64 3.22-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 3-83 I

3.22-2 REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS 3-86 IN ENVIRONMENTAL SAMPLES 4.1-1 INSTRUMENT SURVEILLANCE REQUIREMENTS 4-3 4.1-2 MINIMUM EQUIPMENT TEST FREQUENCY 4-8 4.1-3 MINIMUM SAMPLING FREQUENCY 4-9 4.2-1 CAPSULE ASSEMBLY HITHDRAHAL SCHEDULE AT DAVIS-BESSE 1 4-12b 147- 4.6-1 DIESEL GENERATOR TEST SCHEDULE 4-35d

- 4.6-2 ADDITIONAL RELIABILITY ACTIONS 4-35e

'4.10-1 ENVIRONMENTAL RADIATION MONITORING PROGRAM 4-42 4.10-2 OPERATIONAL ENVIRONMENTAL RADIATION MONITORING PROGRAM 4-22a 4.14-1 DESIGNATED SAFETY RELATED HYDRAULIC SNUBBERS FUNCTIONALLY 4-47d,e TESTED ONLY AS REQUIRED BY THE SNUBBER SEAL REPLACEMENT PROGRAM 4.17-1 MINIMUM NUMBER OF STEAM GENERATORS TO BE INSPECTED 4-56 DURING INSERVICE INSPECTION 4.17-2A STEAM GENERATOR TUBE INSPECTION 4-57 4.17-2B STEAM GENERATOR TUBE INSPECTION (SP!CIAL LIMITED AREA) 4-57a 4.17-3 OTSG AUXILIARY FEEDWATER HEATER SURVEILLANCE 4-57b,c 4.19-1 RADI0 ACTIVE LIQUID EFFLUENT MONITORINC INSTRUMENTATION 4-64 SURVEILLANCE REQUIREMENTS 4.20-1 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 4-66 SURVEILLANCE REQUIREMENTS Proposed Amendment No. 147 ix L

' RANCHO SECO UNIT 1 TECHNICAL' SPECIFICATIONS Limiting Conditions for Operation

1. Reactor Coolant Loop (A) and its associated steam generator and at least one associated reactor coolant pump,

2. Reactor Coolant Loop (B) and its associated steam generator and at least one associated reactor coolant pump,

3. Decay. Heat Removal Loop (A)

4. Decay Heat Removal Loop (B)

Hith less than the above required coolant loops OPERABLE, immediately initiate corrective action to return the required coolant loops to OPERABLE status as soon as possible; be in COLD SHUTDOWN within 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months . ,

3.1.1.6 Reactor Coolant System High Point Vents A. The vent path on Loop A and vent path on Loop B shall be operable and closed during power operation.

B. The vent path on the pressurizer shall be operable and closed during power operation.

C. With one of the above. reactor coolant system vent paths inoperable, STARTUP and/or POWER OPERATION may continue provided the inoperable vent path is maintained closed with power removed from the valve actuator of all the valves in the inoperable vent path; restore the inoperable vent path to OPERABLE status within 30 days. If the status is not restored to operable in 30 days, be in HOT STANDBY within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

D. Hith two or more of the above reactor coolant system vent paths inoperable; maintain the inoperable vent paths closed with power removed from the valve actuators of all the valves in the inoperable vent paths, and restore at least (two) of the vent paths to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . If the status is not restored to operable in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , be in HOT STANDBY within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

147-3.1.1.7 The pressurizer shall be OPERABLE, except when the reactor is in COLD SHUTDOWN. with 3 groups of heaters in two separate banks that are capable of being powered by the diesel generator trains. With the heaters in one bank non-0PERABLE, either restore the bank to OPERABLE status within 3 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

With the heaters in both banks non-0PERABLE, either restore one bank to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Proposed Amendment No. 147 3-2

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation MS11 l

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A reactor coolant pump or decay heat removal pump is required to be in l operation before the boron concentration is reduced by dilution with makeup 4 water. Either pump will provide mixing which will prevent sudden positive reactivity changes caused by dilute coolant reaching the reactor. One decay heat removal pump will circulate the equivalent of the reactor coolant system 1 volume in one half hour or less. (1)

The decay heat removal system suction piping is designed for 300 F and 300 psig; thus, the system can remove decay heat when the reactor coolant system is below this temperature. (2) (3)

One pressurizer code safety valve is capable of preventing overpressurization when the reactor is not critical since its relieving capacity is greater than that required by the sum of the available heat sources which are pump energy, pressurizer heaters, and reactor decay heat. (4) Both pressurizer code safety valves are required to be in service prior to criticality to conform to the system design relief capabilities. The code safety valves prevent overpressure for rod withdrawal accidents. (5) The pressurizer code safety valve lift set point shall be set at 2500 psig 2 1 percent allowance for error and each valve shall be capable of relieving 345,000 lb/hr of saturated steam at a pressure not greater than 3 percent above the set pressure.

The electromatic relief valve setpoint was established to prevent operation of the Safety Valves during transients.

Two pump operation is limited until further ECCS analysis is performed.

When TAV is below 280*F, a single reactor coolant loop or DHR loop provides sufficient heat removal capability for removing decay heat; but single failure considerations require at least two loops be OPERABLE. Thus, if the reactor coolant loops are not OPERABLE, this specification requires two DHR

. cops to be OPERABLE.

The purpose of the high point vents is to vent noncondensible gases from the RCS which may inhibit core cooling during natural circulation. In compliance with 10CFR50 Appendix R the power to all the valve actuators in the vent path has been removed.

147- There are 3 groups of heaters in bank 2, and 3 groups of heaters in bank 3 that are capable of being powered by the diesel generator. Each set of the 3 groups of heaters has a nominal rating of 126 kw which provides assurance that these heaters can be energized during a loss of offsite power condition to maintain natural circulation at HOT SHUTDOWN.

Proposed Amendment No. 147 3-2a

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation REFERENCES (1) FSAR Tables 9.5-2, 4.2-1, 4.2-2, 4.2-4, 4.2-5, 4.2-6 (2) FSAR paragraph 9.5.2.2 and 10.2.2 (3) FSAR paragraph 4.2.5 (4) FSAR paragraph 4.3.8.4 and 4.2.4 (5) FSAR paragraph 4.3.6 and 14.1.2.2.3 Proposed Amendment No. 147 3-2b

RANCHO SECO UNIT 1

. TECHNICAL SPECIFICATIONS ,

Limiting Conditions for Operation l

l 3.7 AUXILIARY ELECTRICAL SYSTEMS j Specification

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3.7.1 ~The reactor shall not be brought critical unless the following conditions are met:

'Acolicabilitv 1

HEATUP until STARTUP.

147- A.- At least two 220 KV lines are in service.

B. The switchyard voltage is 219 KV or above.

C. Both startup transformers, No. 1 and No.2, are in service.

D. Nuclear services 4160V buses'4A, 4A2, 4B, and 482 are operable, i

E. Nuclear services 480V buses 3A, 3A2, 3B, 382, 2A1, 2B1, 2A3, 283, 2A4, and 2B4 are operable.

F. Two separate and independent diesel generator trains (train A is both diesel generators A and A2, train B is both diesel generators B and 82) are operable each with:

1. Separate day tanks containing a minimum volume of 65 percent of tank capacity (265 gallons) of fuel for each A and B and 50 percent of tank capacity (315 gallons) of fuel for A2 and

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2. A separate fuel storage system containing a minimum useable volume of 35,000 gallons of fuel for each A and B and 42,000 gallons of fuel for each A2 and B2.

3. A separate fuel transfer pump for each engine of a train.

G. Nuclear Service batteries BA, BB, BC, BD, BA2, BB2, BC2, and BD2, which supply vital 125 volt DC buses SOA, SOB, SOC, SOD, SOA2, SOB 2, SOC 2, and S002 are charged and in service. ,

H. Each vital 125 volt DC buses SOA, SOC, SOB, SOD, SOA2, SOB 2, SOC 2, and S002 shall have its normal battery charger aligned to it.

I. Nuclear service inverters S1A2, S182, S1C2, and S1D2, and static switches H8TA3, H8TB3, H8TC3, and H8TD3 are operable for 120 volt

- AC vital bus power.

Proposed Amendment No. 147 3-41

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 1 3.7.2 The reactor shall not remain critical unless all of the following requirements are satisfied.

147- A. 220 KV line considerations Specification 3.7.2.A.1 At least two 220 KV lines shall be in-service.

Applicability STARTUP through POWER OPERATIONS Action Should all but one 220 KV line be removed from service a) within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months the operability of the remaining 220 KV line shall be demonstrated by obtaining acceptable results from performing surveillance requirements 4.6.1.A and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter-.

b) within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months obtaining acceptable results from performing surveillance requirement 4.6.3.A.4.

If at least two 220 KV lines are not in service within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , the reactor shall be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and in COLD SHUTDOHN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

Proposed Amendment No. 147 3-41a

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 147- 3.7.2 The reactor shall not rentin critical unless all of the following requirements are satisfied.

B. Diesel Generator Considerations Specification 8.1 Both diesel generator trains shall be OPERABLE prior to leaving COLD SHUTD0HN conditions.

Specification B.2 Diesel generators GEA, and GEB, and GEA2, and GEB2 shall be OPERABLE.

Apolicabili ty STARTUP through POWER OPERATIONS AC_tiDJ1 Should any single diesel generators (GEA, or GEB, or GEA2, or GEB2) become non-0PERABLE due to any cause other than preplanned preventive maintenance or testing, then complete all of the following actions:

a. Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months the operability of at least two 220 KV lines circuits shall be demonstrated by obtaining acceptable results from performing surveillance requirement 4.6.1.A; and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter; or the reactor shall be in HOT SHUTD0HN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTD0HN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b. Hithin 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months obtain acceptable results after performing surveillance requirement 4.6.3. A.4 and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter; or the reactor shall be in HOT SHUTD0HN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

c. If the non-0PEPARLE diesel generator is not restored to OPERABLE STATUS within ? days, i.e., 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months from when the non-0PERABLE condition wat established, the reactor shall be in HOT SHUTD0HN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTD0HN within the following

- 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

Proposed Amendment No. 147 3-41b

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation i

147~ 3.7.2 -The reactor shall not remain critical unless all of the following

-requirements are satisfied.

Specification B.3 Diesel generators GEA2 and GEB2 shall be OPERABLE.

Acolicability STARTUP through P0HER OPERATIONS Action Should diesel generators GEA2 and GEB2 become non-0PERABLE due to any cause other than preplanned preventive maintenance or testing, then complete all of the following actions:

a. Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months the operability of at least two 220 KV lines circuits shall be demonstrated by obtaining acceptable results from performing surveillance requirement 4.6.1.A and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter; or the reactor shall be in HOT SHUTD0HN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTD0HN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b. If both GEA2 and GEB2 diesel generator are non-0PERABLE 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after the second inoperability, the reactor shall be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

c. If one diesel generator (GEA2 or GEB2) is returned to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , follow the 3.7.2.B.2.c 3 day, i.e., 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months LC0 which commenced at the time the remaining non-0PERABLE condition was established.

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L j Proposed Amendment No. 147 3-41c

l.-

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 147- 3.7.2 The reactor shall not remain critical unless all of the following requirements are satisfied.

Soeci fication C. At least two 220KV lines and both diesel generator trains (i.e.,

GEA/GEA2 and GEB/GES2) shall be OPERABLE.

Acolicability STARTUP through POWER OPERATIONS i

Action Should all but one 220 KV line and one diesel generator. train both become non-0PERABLE

a. within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months the operability of the remaining 220 KV line shall be demonstrated by obtaining acceptable results from performing surveillance requirement 4.6.1.A; and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter,

b. within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months the diesel generator train shall be demonstrated to be OPERABLE by obtaining acceptable results from performing surveillance requirement 4.6.3.A.4. This surveillance requirement shall not be performed on diesel generators already running.

If either the 220 KV line or the diesel generator train is not restored to OPERABLE status within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , the reactor shall be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hour:.

With the diesel generator train restored to OPERABLE status within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , follow 3.7.2.A. With the 220 KV line restored to service within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , follow 3.7.2.B.

Proposed Amendment No. 147 3-41d

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 147- 3.7.2 The reactor shall not remain critical unless all of the following requirements are satisfied.

Specification D. At least two 220 KV lines shall be in-service.

Acolicability STARTUP through POWER OPERATIONS Action

.Should all 220 KV lines become non-0PERABLE

a. within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months the operability of the two diesel generator trains shall be demonstrated by sequentially performing surveillance requirement 4.6.3.A.4 and obtaining acceptable results in both cases. This surveillance requirement shall not be performed if the two diesel generator trains are already in-service.

If at least one 220 KV line is not returned to service in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , the reactor shall be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

With one off-site circuit restored to service within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , follow

- 3.7.2.A.

Proposed Amendment No. 147 3-41e

'I' RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 147- 3.7.2 The reactor shall not remain critical unless all of the following requirements are satisfied.

Specification E.1 Diesel generator combinations GEA/GEA2 and GEB/GEB2 shall be i OPERABLE. '

applicabil_ity STARTUP through POWER OPERATIONS 1

estions Should the following diesel generators combinations (GEA/GEA2, GEB/GEB2) become non-0PERABLE due to any cause other than preplanned preventive maintenance or testing, then complete all of the following actions:

a. Hithin 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months the operability of at least two 220 KV lines circuits shall be demonstrated by obtaining acceptable results after performing surveillance requirement 4.6.1.A; or the reactor shall be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b. Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months obtain acceptable results after performing surveillance requirement 4.6.3.A 4; and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter; or the reactor shall be in HOT SHUTDOWN within '

the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOHN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . '

c. If GEA/GEA2, or GEB/GEB2 combinations are non-0PERABLE 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after the first inoperability, the reactor shall be in HOT SHUTDOHN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTD0HN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

d. If one non-0PERABLE diesel generator in the GEA/GEA2, GEB/GEB2 l combination is returned to OPERABLE status within 3 days, i.e.,

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months follow the 3.7.2.B.2.c. 3 days, i.e., 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months LC0 which commenced at the time the remaining non-OPERABLE condition was

- established, i

Proposed Amendment No. 147 3-41f

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 147- 3.7.2 The reactor shall not remain critical unless all of the following requirements are' satisfied.

Specification E.2 Diesel generator pairs GEA/GEB, and GEA/GEB2, and GEB/GEA2 shall be OPERABLE.

Aeolicability STARTUP through POWER OPERATIONS Actions Should diesel generator pairs GEA/GEB, or GEA/GEB2, or GEB/GEA2 become non-0PERABLE due to any cause other than preplanned preventive maintenance or testing, then complete all of the following actions:

a. If GEA/GEB, or GEA/GEB2, or GEB/GEA2 diesel generators are non-0PERABLE 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after the the second inoperability, the reactor shall be in HOT SHUTD0HN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTD0HN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b. If one non-0PERABLE diesel generator in the GEA/GEB non-0PERABLE pair is returned to OPERABLE statue within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , follow the 3.7.2.B.2.c. 168 hour0.00194 days 0.0467 hours 2.777778e-4 weeks 6.3924e-5 months LC0 which ;ommenced at the time the remaining non-0PERABLE condition was established.

1 Proposed Amendment No. 147 3-41g q l

l

, RANCHO SECO UNIT 1 I l' TECHNICAL SPECIFICATIONS j l

Limiting Conditions for Operation l l

147- 3.7.2 The reactor shall not remain critical unless all of the following requirements are satisfied. )

Specification l

F. Both startup transformers shall be in-service. '

Acolicability STARTUP through POWER OPERATIONS Action Should one startup transformer become non-0PERABLE

a. within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months the operability of at least two 220 KV lines shall be demonstrated by obtaining acceptable results from performing surveillance 4.6.1.A; and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter.

b. Within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months the diesel generator trains shall be demonstrated >

to be OPERABLE by obtaining acceptable results from performing surveillance requirement 4.6.3.A.4. This surveillance requirement shall not be perormed on diesel generators already running.

If startup transformer no.1 is not restored to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , the reactor shall be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 205 hours0.00237 days 0.0569 hours 3.38955e-4 weeks 7.80025e-5 months .

If startup transformer no. 2 is not restored to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , the reactor shall be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months

- and in COLD SHUTDOWN within the following 205 hours0.00237 days 0.0569 hours 3.38955e-4 weeks 7.80025e-5 months .

Proposed Amendment No. 147 3-41h

.)

RANCHO SECO UNIT 1 g

TECHNICAL SPECIFICATIONS-Limiting Conditions for Operation 147- 3.7.2 The reactor shall not remain critical unless all of the following requirements are satisfied.

' Specification G. Both startup transformers are OPERABLE.

Aeolicability

.STARTUP through POWER OPERATIONS Action If both startup transformers become non-OPERABLE

a. within one hour take action to place the reactor in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOHN within the following

- 205 hours0.00237 days 0.0569 hours 3.38955e-4 weeks 7.80025e-5 months .

i Proposed Amendment No. 147 3-411

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 147- 3.7.2 The reactor shall not remain critical unless all of the following requirements are satisfied.

Soecificatiort .

H. Nuclear service buses as listed in 3.7.1.D and 3.7.1.E shall be OPERABLE. l Acolicability ,

STARTUP through POWER OPERATIONS Action Should one nuclear service bus become non-OPERABLE for greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , a.. the reactor shall be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

If more than one nuclear service bus from more than one train as listed in 3.7.1.D and 3.7.1.E should become non-OPERABLE,

b. within one hour take action to place the reactor in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following

- 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

f 1

q Proposed Amendment No. 147 3-41j l 1

1

l 4

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 147- 3.7.2 The reactor shall not remain critical unless all of the following i requirements are satisfied.

Specification l I. Nuclear service batteries as listed in 3.7.1.G shall be charged !

and in-service.

Acolicability STARTUP through POWER OPERATIONS Action Should one nuclear service battery become non-0PERABLE for greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ,

a. the reactor shall be in HOT SHUTDOHN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and

'in COLD SHUTDOHN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

If more than one nuclear service battery as listed in 3.7.1.G should become non-OPERABLE, i

b. ' within one hour take action to place the reactor in HOT SHUTD0HN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOHN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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i Proposed Amendment No. 147 3-41k i

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 147- 3.7.2 The reactor shall not remain critical unless all of the following requirements are satisfied.

Specification J. Nuclear service battery chargers as listed in 3.7.1.H shall be OPERABLE.

Acolicability STARTUP through POWER OPERATIONS Action Should one nuclear service battery have no battery charger for greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ,

a. the reactor shall be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

If a standby charger is aligned in place of its normal charger for greater than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months

b. the reactor shall be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

If more than one nuc1 car service battery has no battery charger as listed in 3.7.1.H,

c. within one hour take action to place the reactor in H0T SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the,following

- 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

Proposed Amendment No. 147 3-411 L _ _ - - - -- - - - - - - _ - - - -

e 3 RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation

~147- 3.7.2 The reactor shall not remain critical unless all of the following requirements are satisfied.

3.7.2.K. Nuclear Service Inverters and Static Switches Specification

'3.7.2.K.1 Nuclear service inverters and static switches as listed in 3.7.1.I shall be OPERABLE.

Aoolicability STARTUP through' POWER OPERATIONS Action Should one inverter or static switch become non-0PERABLE for greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ,

a. the reactor shall be in HOT SHUTDOHN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and

- in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

Proposed Amendment No. 147 3 41m

)

RANCHO SECO UNIT 1- l

! TECHNICAL SPECIFICATIONS.

- Limiting Conditions for Operation '

147- 3.7.2 -The reactor shall not remain critical unless all of the following !

requirements are satisfied.

3.7.2.K Nuclear Service Inverters and Static Switches

}

i Specification l

3.7.2.K.2 A static switch shall not be. aligned to the backup source j in place of an OPERABLE nuclear service inverter except ]

during switching periods.

ADDlicabilitV >

STARTUP through POWER OPERATIONS Action If more than one nuclear service inverter or static switch as listed '

in 3.7.1.I should become non-OPERABLE,

a. within one hour take action to place the reactor in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the

- following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

' Proposed Amendment No. 147 3-41n

O RANCHO SECO UNIT 1

. TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 147- ' 3.7.2 The reactor shall not remain critical unless all of the following requirements are satisfied.

I' , Sueci fication L. The switchyard voltage is at least 219KV.

Applicability STARTUP through POWER OPERATIONS Action Should the switchyard voltage drop below 219 KV,

a. positive actions, within the District's procedures, will be implemented in an attempt to return the voltage to at least 219 KV.

If the switchyard voltage goes below 219 KV,.

b. both diesel generator trains shall be demonstrated OPERABLE within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months by obtaining acceptable results from performing.

surveillance requirement 4.6.3.A.4.

Shoul-:i the switchyard voltage not be restored above 219 KV within the next J.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ,

c. the reactor shall be in HOT SHUTDOHN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

T Proposed Amendment No. 147 3-41o

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'l RANCHO SECO 11 NIT 1

{

TECHNICAL SPECIFICATIONS T Limiting Conditions-for Operation l

!- 147 ~ .3.7.3 ..The voltage protection system trip setting shall be as 3tated in Table.

D 3.7-1.

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3.7.4 Voltage Protection System Limiting Conditions .

A. STARTUP and P0HER OPERATION are not permitted unless the minimum requirements and action statements of Table 3.7-2 are met.

B. In the event the number of protective channels falls below that listed in Table 3.7-2, the plant will be brought to a HOT SHUTD0HN within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months ' .

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Proposed Amendment No. 147 3-42

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation Bases The auxiliary electrical power systems are arranged so that no single failure can inactivate enough safety features equipment to jeopardize plant safety.

The normal source of power to the redundant nuclear service loads is by the two startup' transformers to connect the 220-KV station switchyard. All of the i 147- normal power supply to plant auxiliary loads can be provided through the two unit auxiliary transformers connected to the generator buses. Emergency power for the nuclear service loads is obtained from two on-site diesel generator trains (tre.in A is both diesel generators A and A2, train B 1s both diesel

- generators B and B2). Since the startup transformers are sized to carry full plant auxiliary loads, if plant auxiliaries' power is not available from the -

unit auxiliary transformer, it will be obtained from the startup transformers.

The five 220-KV transmission lines are not under the direct control of the Rancho Seco station. Therefore, all five cannot be assumed to available at j all times. However, extensive reliability and protective features are l utilized so that the probability of losing more than one source of 220-KV power from faults is low. By requiring that two 220-KV lines are in service prior to startup, one circuit will be immediately available following a loss of the onsite alternating current diesel power supplies and the other offsite 220-KV line. If there is a loss of all 220-KV remote connections, power to the safety features will be supplied by the c'iesel generator trains. The 35,000 gallons.of fuel stored in each storage tank permit operation of the 147- diesel generators A and B for seven days. The 42,000 gallons of fuel stored in each storage tank permit operation of the diesel generators A2 and B2 for

- seven days. It is considered unlikely not to be Alt to secure fuel oil from an outside source during this time under the worst of weather conditions.

147- The set of eight 125 volt DC control buses (SOA, SOB, SOC, S00, SOA2,

- SOB 2, SOC 2, and SOD 2) are arranged so that loss of one bus will not preclude safe shutdown or operation of safety features systems. During periods when- .

one plant battery is de-energized for test or maintenance, the associated 125 i volt DC bus can be supplied from its battery charger, j 4

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l Proposed Amendment No. 147 1 3-42a

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' RANCHO SECO UNIT 1

' TECHNICAL SPECIFICATIONS TABLE 3.7-1

.g.

VOLTAGE PROTECTION SYSTEM RELAY TRIP VALUES EQUIVALENT TIME DELAY UNDERVOLTAGE RELAYS 4160 BUS VOLTS (SECONDS) NOTES 1 (VOLTS) 147- A. Definite Time Delay Trip-Set Point 3771 2 38 5.0 0.5 (Drop Out)

B. ' Inverse 3771

38 N/A Time Delay.

Trip Set Point-(Drop.0ut)

.70 Percent of Set Point 2640 e 27 3.0 x 0.5.

~

' NOTE 1 - For bus tripping, an additional 0.5. second time delay must be added.

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, Proposed Amendment No. 147 l 3-42b L__________m.m_.-_ _ _ _ _ _ _ _ - _ _

'147-RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS TABLE 3.7-2 (Note 1)

Total No. of Minimum Functional Number of Relays / Channels Channels Action Unit Channels Channel To Trip Operable 147~ Undervoltage 3/ Bus 2 2/ Bus 2 A ACTION STATEMENTS Action A - Hith the number of OPERABLE channels one less than the total Number of Channels, operation may proceed provided both the following conditions are satisfied:

a. The Inoperable Channel is placed in the tripped condition within one hour.

b. The Minimum Channels OPERABLE requirement is met; however, one additional channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for i surveillance testing.

Note 1: The table is not applicable when the plant is in cold shutdown.

Proposed Amendment No. 147 3-42c

l RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 1474 Each redundant pair ("A" and "C", "B" and "D") of the eight 125 volt DC control buses (SOA and SOC, SOB and SOD, SOA2 and SOC 2, and S082 and S0D2) has a standby battery charger in addition to its normal battery charger. On the loss of power from one battery charger per pair the standby battery charger is put in service. However, the standby charge can be aligned in place of its normal charger for only 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months because the standby battery charge is powered from a different diesel generator than the normal battery charger. There are potential interactions after 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months that could occur upon the loss-of-off-site power and a single diesel generator failure. This situation has not been analyzed but by limiting the time this configuration could exist, the probability of occurence is sufficiently low to justify

- limited operation in this condition.

During periods of station operation under the condition of electrical system degradation, as described above in Specification 3.7.2, the operating action required is to start and run sufficient standby power supplies so as not to compromise the safety of the plant. As seen in Specification 3.7.2, a time i limit is placeJ on operation during certain degraded conditions based on the reliability of the available power supply.

147- Four nuclear service inverters (S1A2, S182, S1C2, and S1D2) and static switches (H8TA3, H8TB3, H8TC3, and H8TD3) are required to be operable to power the 120 volt AC vital buses. The nuclear service inverters are powered from diesel generators A2 and B2 and the static switches are powered from diesel generators A and B. This design ensures that upon loss of an inverter or a single diesel generator the 120 volt AC vital buses will continue to l receive power and that there are no system interactions. One nuclear service !

inverter or static switch is permitted to be incperable for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

The static switch is only used as a backup for the inverter. It is not permitted to be used when an inverter is operable except for switching period j because it receives power from the nuclear service 480V buses and there is no battery backup available.

l The voltage protection system is designed to isolate the nuclear service buses from the startup transformers before the voltage drops below the ,

allowable operating limit of the equipment. The undervoltage protection for the 4160 volt nuclear service buses is 3771 e 38 volts. This corresponds

- to a nominal switchyard voltage range of 219 KV.

REFERENCE FSAR, Section 8 Proposed Amendment No. 147 3-43

7 RANCHO SECO UNIT 1-TECHNICAL SPECIFICATIONS-Limiting Conditions for Operation Table 3.14-1 (Continued)

FIRE DETECTION INSTRUMENTS FOR SAFETY SYSTEMS Minimum Operable Zone Instrument Location Heat Flame Smoke 75-1 B Switchgear Room (NSEB) 0 0 1 75-2 BB2 Battery Room (NSEB) 0 0 1 75-3 BD2 Battery Room (NSEB) 0 0 1 76-1 A Switchgear Room (NSEB) 0 0 1 76-2 .BA2 Battery Room (NSEB) 0 0 1 76-3 BC2 Battery Roua (NSEB) 0 0 1 77-1 North B Electrical Equipment Room (NSEB) 0 0 1 77-2 South.B Electrical Equipment Room (NSEB) 0 0 1 78-1 North A Electrical Equipment Room (NSEB) 0 0 1 78-2 South A Electrical Equipment Roon. (NSEB) 0 0 1 81 B Cable Tunnel / Shaft (NSEB) 0 0 3 82 A Cable Tunnel / Shaft (NSEB) 0 0 3 84-2 B Mechanical Equipment Room (NSEB) 0 0 1 84-3 A Mechanical Equipment Room (NSEB) 0 0 1 147* 105 Diesel Generator Building 2 3 2

.106 Diesel Generator Building 2 3 2 1

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Proposed Amendment No. 147 3-55a f

l RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.14.3 Sorav and Sorinkler Systems j j

Specification 3.14.3.1 The spray and/or sprinkler systems located in the following )

areas shall be OPERABLE:

a. Control Room (Zone 3) {

b. Controlled Area, Mezzanine Level (Zone 20) .

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c. Main Lube Oil Area, Grade Level (Zone 32)

d. Grade Level (Zone 34)

e. North Diesel Room (Zone 40)

f. South Diesel Room (Zone 41) 9 West Controlled Area, Grade Level (Zone 42)

h. East ',ontrolled Area, Grade Level (Zone 43)

1. South and East -20' Level (Zone 46)

j. NSEB B Cable Tunnel / Shaft (Zone 81)

k. 'NSEB A Cable Tunnel / Shaft (Zone 82)

1. NSEB Mechanical Equipment' Rooms A and B (Zone 84) 147- m. Diesel Generator Building (Zone 105)

n. Diesel Generator Building (Zone 106) l 3.14.3.2 Hith one or more of the above, items a through f, required spray and/or sprinkler systems are inoperable, within one hour establish a continuous fire watch with backup fire suppression equipment for those areas in which redundant systems or components required to safely shut down and cool down the plant could be damaged; for other

. areas, establish an hourly fire watch patrol. Restore the system to OPERABLE status within 14 days or, in lieu of any other report required by Specification 6.9, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.5.E within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

3.14.4 CO2 System Specification 3.14.4.1 The CO2 systems located in the following areas shall be OPERABLE with a minimum capacity of 66 and a minimum pressure of 275 psig in '

the storage tank:

a. Zone 12 West DC Control Room Hezzanine Level !

b. Zone 13 Hest 480 VAC Room Mezzanine Level

c. Zone 14 West Cable Tray Area

d. Zone 15 East Cable Tray Area

e. Zone 16 East 480 VAC Room Mezzanine Level

f. Zone 17 East DC Control Room Mezzanine Level <

g. Zone 36 West Battery Room Grade Level Proposed Amendment No. 147 3-56

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS-Limiting Conditions for Operation Table 3.14-2 (Continued). ;

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I- INSIDE BUILDING FIRE HOSE STATIONS l ID No. Location 147-- III Diesel Generator Building Hose Stations FPHS-D-001 Train A' Engine Room Elevation O' FPHS-D-002 ' Train A Control Room Elevation O' FPHS-D-003 ~ Train.A Mezzanine Elevation 18'6" FPHS-D-004 Train B Engine Room Elevation O' FPHS-D-005 Train B Control Room Elevation O'

- FPHS-D-006 Train B Mezzanine Elevation 18'6"

- Proposed Amendment No. 147 3-57b

147-RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.27 Nuclear Service Electrical Buildina Emeraency Heatina Ventilation and Air Conditioning System-Specification 3.27.1 Both Nuclear Service Electrical Building Emargency Heating Ventilation and Air Conditioning trains shall be OPERABLE.

Applicability HEATUP through POWER OPERATIONS Action:

a. With one Nuclear Service Electrical Building Emergency Heating l Ventilation and Air Conditioning train non-0PERABLE, restore the train to OPERABLE status within 7 days or be in at least HOT STANDBY.within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTD0HN within following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b. Hith both Nuclear Service Electrical Building Emergency Heating Ver.tilation and Air Conditioning trains non-0PERABLE, restore the trains to OPERABLE status within 3.5 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . ,

i Bases

.The Nuclear Service Electrical Building (NSEB) Emergency Heating Ventilation and Air Conditioning System is required to provide cooling

- - to protect required electrical components in the~ NSEB.

i Proposed Amendment No. 147 3-93

RANCHO SECO UNIT 1

" TECHNICAL SPECIFICATIONS Limiting Conditions for Operation

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147- 3.28 TDI Diesel Generator Control Room Essential Ventilation System Specification 3.28.1 Both TDI Diesel Generator Control Room Essential Ventilation trains shall be OPERABLE.

Aeolicability HEATUP through POWER OPERATIONS Action

a. ,With one TDI Diesel Generator Control Room Essential Ventilation train non-0PERABLE, demonstrate the ope ability of the remaining train. Restore the non-0PERABLE train to OPERABLE status.within 3 days or be in at least HOT 3HUTDOWN within six hours and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ,

b. With both TDI Diesel Generator Control Room Essertial Ventilation trains non-OPERABLE, restore at least one non-0PERABLE train to OPERABLE status within 2 hoors or be in at least HOT SHUTDOWN within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD S30TD0HN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . With one non-0PERABLE train restored to OPERABLE status, continue with Action a. Obove using the time the remaining non-OPERABLE condition wac established as the start of the LCO.

Bases The TDI Diesel Generator Control Room Essential Ventilation System is required to maintain the temperature in the control room below 122*F ,

- to protect required electrical components.

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Proposed Amendment No. 147 3-93a

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS ~

Surveillance Standards-TABLE 4.1-1 (Continued)

INSTRUMENT SURVEILLANCE REQUIREMENTS Channel Description Check Test Calibrate Remarks

, - 57 Voltage Protection (1) Test using undervoltage relays 147* a. - Undervoltage Relay M(1) N/A R " TRIP TEST." No quantitative.

Setpoint~ .

measurements.

< b. Undervoltage Relay M(1) N/A R

=- Time Delay S8. Containment Area High S M(1) R (1) Test using installed source Range Monitor

59. Wide Range Containment M N/A R Water Level

60. Containment Hydrogen S M Q

' Analyzer i

61. Emergency Sump Level M: N/A R ;

62.: Containment Wide range M N/A R Pressure Monitor / Recorder

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63. High' Range Noble Gas S M k Effluent Monitors

- RB Exhaust Stack

- Aux. Building Stack

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- Radwaste' Vent

64. Main Steam Line Radiation S M(1) R (1) Test using installed source Monitors

65. Subcooling Margin Monitors M N/A R

66. ' Incore Thermocouple M N/A R j

67. Low Temperature Over N/A (1) R (1) Prior to cooldown i Pressure Protection j

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$ = Each shift M = Monthly P = Prior to each startup if not done previous week D = Daily Q = Quarterly R = Once during the refueling interval W = Weekly SY = Semiannual Proposed Amendment No. 147 4-7c 1

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards

2. The test will be considered satisfactory if control 5 board indication verifies that all components have responded to the actuation signal and the appropriate breakers shall have completed their travel.

3. Additionally it shall be verified that the NSCH flow through each operating cooler exceeds 1400 gpm and air flow through the cooler exce d 40,000 cfm.

4.5.2.2 _Camponent Tests A. Testing At least quarterly, Inservice testing of Reactor Building Spray pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g), except where specific writte relief has been granted by the NRC pursuant to 10 CFR h., Section 50.55a(g)(6)(i).

B. Flow Path Verification Following Inservice testing of pumps and valves as required by paragraph 4.5.2.2.A, required flow paths shall be demonstrated operable by verifying that each valve (manual, power-actuated or automatic) in the flow path that is not locked in position is in its normal operating position.

Positions of locked valves shall be verified in accordance with the provision of Section XI of the ASME Boiler and Pressure Vessel Code.

147- C. The pressurizer shall be tested as follows:

1. The pressurizer water level shall be determined to be within its limits at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

2. The power supply for the nuclear service backed pressurizer heaters shall be demonstrated OPERABLE at least once per refueling interval by using the Nuclear

- Service Bus to energize the heaters.

Proposed Amendment No. 147 4-30

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards hsn The Reactor Building emergency cooling systems and Reactor Building spray system are designed to remove the heat in the containment atmosphgrp _to prevent the building pressure from exceeding the design pressure.t u ,

The delivery capability of one Reactor Building spray pump at a time can be tested by opening the valves in the line from the borated water storage tank, opening the corresponding valve in the test line, and starting the corresponding pump. Pump discharge pressure and flow indication demonstrate performance.

With the pumps shutdown and the borated water storage tank outlet valves closed, the Reactor Building spray injection valves can each be opened and closed by operator action. With the Reactor Building spray inlet valves closed, air can be blown through the test connections of the Reactor Building spray nozzles to demonstrate that the flow paths are open.

The equipment, piping, valves, and instrumentation of the Reactor Building emergency cooling system are arranged so that they can be visually inspected. The cooling units and associated piping are located outside the secondary concrete shield. Personnel can enter the Reactor Building during power operations to inspect and maintain this equipment. The nuclear service cooling water piping and valves outside the Reactor Building are inspectable at all times. 4 147- The operability of the nuclear service bus backed pressurizer heaters is

-- demonstrated by energizing the heaters once per refueling interval. <

l REFERENCES I J

(1) FSAR, section 9.

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Proposed Amendment No. 147 l 4-31 ;

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 4.6 EMERGENCY POWER SYSTEM PERIODIC TESTING Specification 147- 4.6.1 Offsite Power Sources L A. Each of the 220 KV lines required by 3.7.1.A shall be:

Determined OPERABLE at least weekly by verifying correct breaker alignments and indicated power availability, and B. Each Start-up Transformer required in 3.7.1.C shall be demonstrated OPERABLE at least once per REFUELING interval by transferring nuclear service buses as listed in 3.7.1.D from the normal startup transformer supply circuit to the alternate startup transformer supply circuit.

analisability

- HEATUP through P0HER OPERATIONS l

Proposed Amendment No. 147 4-34

RANCHO SECO UNIT-1 TECHNICAL SPECIFICATIONS Surveillance Standards t 4.6 Emergency Power System Periodic' Testing (Continued) 147-

-Specifications 4 '. 6. 2 -- Nuclear service buses required by 3.7.1.D and 3.7.1.E shall be determined to be OPERABLE at least weekly by verifying correct -

breaker alignment and indicated power availability.

Acolicabilitv-

- HEATUP through.P0HER'0PERATIONS Proposed Amendment No. 147 4-34a

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 147-+

4.6. Emergency Power System Periodic Testing (Cor tiriued) 4.6.3- Diesel generator operability Acolicability At all times Specifications Each diesel generator train shall be demonstrated OPERABLE by verifying that both diesel generators in the train are OPERABLE (GEA and GEA2, GEB and GEB2).

A. In accordance with the frequency specified in Table 4.6-1 by:

1. Verifying the fuel level in the day tank,

2. Verifying the fuel level in the fuel storage tank, 3.* Verifying the fuel transfer pump starts and transfers fuel from the storage system to the day tank,

4. Verifying the diesel starts from a manual signal and accelerates to a nominal 900 rpm for A and B and a nominal 450 rpm for A2 and B2. The generator voltage and frequency shall be 4160 ( 420) volts and 60 (11.2) Hz after the start signal. (Note 1) 5.* Verifying the generator is synchronized and operates with its load between 2550 and 2750 kw for A and B and 3000 and 3300 kw for A2 and B2 for at least 60 minutes,(Note 1). .

6. Verifying the diesel generator is aligned to provide emergency l power to the nuclear service buses at the conclusion of the test.

7. At the number of failures for the inoperable diesel generator indicated in Table 4.6-2 perform the Additional Reliability Actions prescribed in Table 4.6-2.

Note 1 All planned engine starts may be preceded by an engine prelube period. With the exception of once per 184 days, all planned I

engine starts may De preceded by warmup procedures recommended by the manufacturer and may also include slow starting and gradual loading so that mechanical stress and wear on the diesel engine is minimized. The testing performed once every 184 days shall include fast starting (less than or equal to 10 seconds).

Surveillance shall not be performed when a diesel generator train or startup transformer is not operable in accordance with TS3.7.2.

Proposed Amendment No. 147 4-34b 1

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 147-B. Fuel Oil Storage

1. By removing accumulated water:

a) From the day tank at least monthly and after each occasior, when the diesel is operated for greater than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , and b) From the storage tank at least monthly.

2. By sampling new fuel oil in accordance with ASTM D4057-81 (1981) prior to addition to the storage tanks and:

a) By verifying in accordance with the tests specified in ASTM D975-81 prior to addition to the storage tanks that the sample has:

i) An absolute specific gravity at 60/60*F of greater than or equal to 0.83 but less than or equal to 0.90 or an API gravity at 60*F of greater than or equal to 26 degrees but less than or equal to 38 degrees in accordance with ASTli D1298-77.

ii) A kinematic viscosity at 40*C of greater than or equal to 1.9 centistokes, but less than or equal to 4.1 centistokes, or Saybolt Viscosity, (SUS at 100*F) of greater than or equal to 32.6, but less than or equal to 40.1 measured in accordance with ASTM D-88-81.

iii) A flash point equal to or greater than 125'F, and iv) Hater and sediment of less than or equal to

- 0.05 percent by volume.

Proposed Amendment No. 147 4-35

RANCHO SECO UNIT'l i TECHNICAL SPECIFICATIONS ;

Surveillance Standards 147* b) By verifying within 31 days of obtaining the sample that the other properties specified-in' Table 1 of 3 ASTM D975-81 are met when tested in accordance with -

ASTM D975-81, except that the analysis for sulfur- '] .

may be performed in accordance with ASTM D1552-79 or ASTM D2622-82. -(Note 2)

3. At least MONTHLY by obtaining a sample of fuel oil from the storage tanks in accordance with ASTM D4057-81 (1981), and verifying that total particulate contamination is less than 10 mg/ liter when checked in accordance with ASTM D2276-73 (1978), Method A.

Note 2 If one or more properties are out of specification, within 62 days of obtaining the bad fuel oil, verify that an additional sample of fuel. oil from the fuel oil storage tank is within specification, cr empty and refill the tank with a new shipment of fuel oil

- within 77 days of the original out-of-specification sample.

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Proposed Amendment No. 147 4-35a

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RANCHO SECO UNIT 1

. TECHNICAL SPECIFICATIONS Surveillance Standards-

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L147 . 'C. At each refueling. interval, by:

1. Diesel Generator Inspections a) Subjecting the diesel generators A and B to an inspection in accordance with procedures prepared '

i in conjunction with the maintenance recommendations provided byLits manufacturer for this class'of. '

standby service. I

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b) Subjecting the diesel generators A2 and B2 to an inspection in accordance with procedures prepared-in conjunction with the maintenance and surveillance program recommended by the TDI Owners i Group in " Design Revision and-Quality Revalidation Report for Rancho Seco," Appendix II.

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Proposed Amendment No. 147 l 4-35b i

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 147- 2. Simulating a loss of off-site power in conjunction with a safety features actuation signal, (Note 4, Note 6) and I a) Verifying de-energization of the nuclear service buses and operation of the load shedding circuitry.

b) Verifying the diesel starts on the auto-start signal (Note 3), energizes the nuclear service buses, verifying proper operation of the automatic load sequencing circuitry, and operates for greater than or equal to 5 minutes in this condition.

After energization, the steady state voltage and frequency of the emergency buses shall be maintained at 4160 ( 420) volts and 60 ( 1.2) Hz during this test.

- 3. Simulating a loss of off-site power and verifying that on interruption of the emergency power sources the loads are shed from the nuclear services buses in accordance with design requirements and that subsequent loading of the emergency power sources is through the automatic load sequencing circuitry. The diesel generator will be operated for at least 5 minutes in this condition.

(Note 1) 147~ 4. Verifying the diesel generator operates for at least 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (Note 1). During the first 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of this test, the diesel generator shall be loaded between 2650 and 2850 kw for A and B and 3000 and 3300 kw for A2 and B2 and for the remaining 22 hours2.546296e-4 days 0.00611 hours 3.637566e-5 weeks 8.371e-6 months of this test, the diesel generator shall be loaded between 2550 and 2750kw for A !

and B and 3000 and 3300kw for A2 and B2.

i Note 1 All planned engine starts may be preceded by an engine prelube l period. With the exception of once per 184 days, all planned engine starts may be preceded by warmup procedures recommended by the manufacturer and may also include slow starting and gradual '

loading so that mechanical stress and wear on the diesel engine is minimized. The testing performed once every 184 days shall

- include fast starting (less than or equal to 10 seconds).

Note 3 All planned engine starts for the purpose of this surveillance testing may be preceded by an engine prelube period. The testing

< 147* shall include fast starting (less than or equal to 10 seconds). ,

i Note 4 Prior to the performance of this test the diesel generators shall be operated at between 2550 and 2750 kw for A and B and 3000 and 3300 kw for A2 and B2 for at least 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and until engine operating temperatures have stabilized.

Note 6 When the test required by specification 4.6.3.E is performed, then the test required by specification 4.6.3.C.2 is not required to be performed.

- Proposed Amendment No. 147 4-35c

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 147- D. At least once per 10 years, by starting all four diesel generators simultaneously (Note 3) and verifying that they accelerate to a nominal 900 rpm for A and B and a nominal 450 rpm for A2 and 82 within 10 seconds after the start signal.

The generator voltage and frequency shall be 4160 ( 420) volts and 60 (11.2) Hz within 10.0 seconds after the start signal.

E. At least once per 10 years simulating a loss of off-site power in conjunction with a simulated SFAS (Note 5), and

1. Ve-ifying de-energization of the nuclear service buses and load shedding from the nuclear service buses.

2. Verifying the diesel starts on the auto-start signal, energizes the nuclear service buses with permanently connected loads, loads through the load sequencer and operates for greater than or equal to 5 minutes while its generator is loaded with the emergency loads. After energization, the steady state voltage and frequency of the emergency buses shall be maintained at 4160 ( 420) volts and 60 (i 1.2) Hz during this test.

3. Verifying for the A and B diesel generators that all automatic diesel generator trips, except engine overspeed, ground fault and generator differential, and verifying for the diesel generators A2 and B2 that all automatic diesel generator trips, except engine overspeed, low lube oil pressure and generator '

differential, are automatically bypassed with an SFAS.

Note 3 All planned engine starts for the purpose of this surveillance testing may be preceded by an engine prelube period. The testing shall include fast starting (less than or equal to 10 seconds).

Note 5 All planned engine starts for the purpose of this surveillance testing may be preceded by an engine prelube period. The testing shall include fast starting (in less than or equal to 10 seconds) and fast loading through the sequencer.

Proposed Amendment No. 147 4-35d i

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i s RANCHO SECO UNIT-1 TECHNICAL' SPECIFICATIONS Surveillance Standards.

Specification

.147- 4.6.4 Batteries in'the 125 volt DC systems shall be tested as follows:

A. The voltage and specific gravity of each pilot cell shall be measured and recorded. weekly.

B. The specific gravity,' level and voltage of each cell shall be measured and recorded every month.

C. Each time data are recorded, new data shall be compared with old to detect signs of deterioration.

D. During each refueling interval, the battery shall be subjected to a rated load or equivalent test. The battery voltage as a function of time shall be monitored to establish that the battery performs as expected.

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Proposed Amendment 147 4-35e

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards L Bases

' - 147- The operability of the 220KV lines, the nuclear service 4160V buses, and the nuclear service 480V buses are demonstrated by verifying correct breaker alignments and indicated power availability. Surveillance 4.6.1.8 can only be performed during a refueling shutdown when both diesel generator trains i are operable or the core is flooded to 37 feet to ensure the required decay

- heat removal capability is available.

The tests specified are designed to demonstrate that the diesel generators will_ provide power for operation of safety features equipment. They also i assure that the emergency generator control system and the control systems 1~

for the safety features equipment will function automatically in the event of a loss of all normal a-c station service power, and upon receipt of a safety features actuation signal. The testing frequency specified is intended to identify before it can result in a system failure. The fuel oil supply, starting circuits and controls are continuously monitored and any faults are alarmed and indicated. An abnormal condition in these systems would be signaled without having to place the diesel generators on test.

147- The limiting of the maximum load on the TDI diesel generators A2 and B2 to less than the qualified load of 3300 kw provides assurance that the crankshafts will stay within the proven limits for high-cycle fatigue cracks. '

Diesel generators A2 and B2 will be loaded during surveillance testing between 3000 and 3300 KH which provides assurance that the qualified load of 3300 KH will not be exceeded.

At least once per 10 years a diesel generator test will be performed simulating a loss of off-site power in conjunction with a simulated SFAS and loading of actual loads to the maximum extent possible without damaging plant systems (i.e., use of recirculation flow or manual valving out a system to protect plant components).

Precipitous failure of the plant battery is extremely unlikely. The surveillance specified is that which has been demonstrated over the years to provide an indication of a cell becoming unserviceable long before it fails.

REFERENCE (1) IEEE 308 Proposed Amendment No. 147 4-35f

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-RANCHO SECO UNIT 1

' TECHNICAL SPECIFICATIONS Surveillance Standards a

'1474 ' ELECTRIC POWER SYSTEMS l

Table 4.6-1 I l

DIESEL GENERATOR TEST SCHEDULE Number of Failure in Last-20 Valid Tests

Test Freanency 1 At least MONTHLY 2 At least HEEKLY**

Criteria for determining number of failures and number of valid tests shall be in accordance with Regulatory Position C.2.e of Regulatory Guide 1.108, Revision 1. August 1977, where the number of tests and failures is determined on a per diesel generator basis. For the purposes of this test schedule, only valid tests conducted after the license amendment issuance date shall be included in the computation of the "last 20 valid tests."

- This test frequency shall be maintained until seven consecutive failure free demands have been performed and the number of failures in the last 20 valid demands has been reduced to one or less.

1 Proposed Amendment No. 147 4-35g ,

k RANCHO SECO UNIT 1

+ TECHNICAL SPECIFICATIONS

. Surveillance Standards 147-TABLE 4.6 ADDITIONAL RELIABILITY ACTIONS No 'of: failures No. of. failures inulast 20 in last'100-valid-test

valid' tests Action l

3 6 Hithin'14 days prepare and maintain a report for NRC audit describing 'the -

-diesel generator reliability improvement program implemented at the site. Minimum requirements-for the-report are indicated in Note 1 to

this table.

J' 5 , 11 Perform'a requalification test program for the affected diesel generator. Requalification test:

program requirements.are indicated in Note ~2 to-this table.

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For the purposes of this schedule, only valid tests conducted after l the license amendment issuance date shall be included in the computation of the~"last 20 valid tests" and "last 100 valid tests."

L Proposed Amendment No. 147 4-35h

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 1474 NOTE 1 TO TABLE 4.6-2 REPORTING REQUIREMENT As a minimum the Reliability Improvement Program report for NRC audit shall

. include:

a) a summary of all tests (valid and invalid) that occurred within the time period over which the last 20/100 valid tests were performed.

b) analysis of failures and determination of root causes of failures c) evaluation of each of the recommendations of NUREG/CR-0660, " Enhancement of Onsite Emergency Diesel Generator Reliability in Operating Reactors,"

with respect to their application to the Plant d)- identification of all actions taken or to be taken to 1) correct the root causes of failures defined in b) above and 2) achieve a general

, improvement of diesel generator reliability e) the schedule for implementation of each action from d) above f) an assessment of the existing reliability of electric power to engineered-safety-feature equipment Once a licensee has prepared and maintain an initial report detailing the diesel generator reliability improvement program at his site, as defined above, the licensee need prepare only a supplemental report within 14 days after each failure during a valid demand for so long as the affected diesel generator unit continues-to violate the criteria (3/20 or 6/100) for the reliability improvement program remedial action. The supplemental report need only update the failure / demand history for the affected diesel generator unit since the last report for that diesel generator. The supplemental report shall also present an analysis of the failure (s) with a root cause determination, if possible, and shall delineate any further procedural, hardware or operational changes to be incorporated into the site diesel generator improvement program and the schedule for implementation of those changes.

In addition to the above, submit a yearly data report on the diesel generator reliability.

1 Proposed Amendment No. 147, 4-351

i RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS L' Surveillance Standards NOTE 2 TO TABLE 4.6-2 DIESEL GENERATOR RE00ALIFICATION PROGRAM (1) Perform seven consecutive successful demands without a failure within I 30 days of diesel generator being restored to operable status from the last failure and fourteen consecutive successful demands without a 147-- failure within 75 days of diesel generator being restored to operable i status from the last failure.

(2) If one failure occurs during the first seven tests in the requalification test program, perform seven successful demands without 147-~ an additional failure within 30 days of diesel generator being restored to operable status after the first failure of the requalification test program and fourteen consecutive successful l demands without a failure within 75 days of being restored to operable status after the first failure of the requalification test program.

(3)- If one failure occurs during the second seven tests (tests 8 through

14) of (1) above, perform fourteen consecutive successful demands without an additional failure within 75 days of the failure which occurred during the requalification testing.

(4) Following the:second failure during the requalification test program declare the diesel. generator inoperable and follow the applicable requirements of Specification 3.7.2. The diesel generator shall not be considered operable until the diesel generator has successfully requalified.

(5) During requalification testing the diesel generator should not be 147-- tested more frequently than at 24-hour intervals each.

After a diesel genrator has been successfully requalified, subsequent repeated requalification tests will not be required for that diesel generator under the following conditions:

147-- (a) The number of failures in the last 20 valid test: is less than 5.

147-- (b) The number of failures in the last 100 valid tests is less than 11.

(c) In the event that following successful requalification of a diesel generator, the number of failures is still in excess of the remedial action criteria (a and/or b above) the following exception will be allowed until the diesel generator is no longer in violation of the remedial action criteria (a and/or b above).

Requalifiction testing will not be required provided that after each valid 147-~ tests the number of failures in the last 20 and/or 100 valid tests has not

'incntaird. Once the diesel generator is no-longer in violation of the remedial action criteria above the provisions of those criteria alone will prevail.

Proposed Amendment No. 147 4-35j

i RANCHO SECO UNIT 1 I

TECHNICAL SPECIFICATIONS Surveillance Standards .

Specification (Continued) j 4.10.1 C. 2. (b) Verify that the HEPA filter bank removes 199.9 percent of the 00P when tested in-place in l accordance with ANSI N510 while cperating the j filter train at a flow rate of 3200 cfm 10 percent.

D. Started on a manual signal and operated for 15 minutes in each 31-day period.

Bases -

The purpose of the Control Room /TSC Emergency Filtering System is to limit the particulate and gaseous fission produris and toxic products to which the Control Room area and Technical Support Canter would be subjected during an accidental radioactive or chemical release.in or near the Auxiliary Building. The system is designed with two redundant filter trains each of which consists of a moisture separator, a heater, a high efficiency particulate filter, two banks of charcoal filtars, a second high efficiency '

particulate filter and a booster fan to pressurize the Control Room and Technical Support Center with outside air.

147-* Because this system is not normally operated, a periodic test is required to ensure its operability when needed. Monthly testing of this system will

! show that the system is available for its designed safety action. During this test the system will be observed for unusual or excessive noise or vibration when the fan motors are running. The flow of 1600 cfm makeup air was-selected to limit the maximum radiation dose to occupants of the Control Room /TSC in an accident. For this analysis, both charcoal filter banks were assumed to provide DF's of 10, while the HEPA filter DF is assumed to be 100. The laboratory analysis to show 195 percent removal of methyl radioiodide is necessary to receive credit for a DF of 10.

Refueling interval testing will verify the methyl iodide removal efficiency of the charcoal and the amount of leakage past the enarcoal and HEPA filters j are at least equal to the design values, j 147- The filtering system is automatically started and the normal system isolated

- when the radiation level or when the Chlorine level increase.

The testing required after painting, fire or chemical release, is not to be interpreted to include minor touch-up painting, housekeeping chemicals and detergents, or other routine maintenance or housekeeping activities.

Proposed Amendment No. 147 4-41b

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 4.31 NUCLEAR SERVICE ELECTRICAL BUILDING EMERGENCY HEATING VENTILATION AND AIR CONDITIONING 5 specification 4.31.1 The NSEB Emergency HVAC shall be demonstrated operable at least once per 31 days by initiating flow through the essential air handling unit and verifying:

1. Verify that the air handling unit maintains a flow rate cf 24,500 cfm 10 percent.

2. Verify that the condensing unit is operational.

Applicability At all times Bases The purpose of the Emergency Nuclear Service Electrical Building Emergency HVAC is to limit high temperatures which the building would be subjected to upon loss of normal cooling. The high temperatures will affect the environmental qualification of safety related electronic equipment housed within the NSEB which is used to support the Control Room /TSC upon accident conditions. The system is designed with an air handling unit and a condensing unit wh'ch are activated upon high temperature signals.

Sin:e this system is not normally operated, a periodic test is required to ensure its operability when needed. Monthly testing of this system will show that the system is available for its safety action. During this test the system will be observed for unusual or excessive noise or vibration when the fan motors are running. The air flow of 24,500 cfm was selected to limit the temperatures in the building to 80*F maximum (with the exception of the cable shafts).

The system is automatically started when the temperature in the NSEB 147-- Switchgear Room exceeds 95'F.

Proposed Amendment No. 147 4-91

147- ,

1 RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS l

Surveillance Standards 4.32 TDI DIESEL GENERATOR CONTROL ROOM ESSENTIAL VENTILATION SYSTEM Specification 4.32.1 The Diesel Generator Control Room Essential Ventilation System shall be demonstrated operable at least once per 31 days by initiating flow through the essential air handling unit by verifying that the air handling unit maintains a flow rate greater than the low flow alarm setpoint.

Acolicability At all times Bases The purpose of the TDI Diesel Generator Control Room Essential Ventilation System is to limit high temperatures which the local control room would be subjected to upon loss of normal cooling. The high temperatures will affect the environmental qualification of safety related electronic equipment housed witnin -the Diesel Generator Control Room. This Control Room is designed with an air handling unit which is activated upon a high temperature signal.

Since this system is not normally operated, a periodic test is required to ensure its operability when needed. Monthly testing of this system will show that the system is available for its safety action. During this test the system will be observed for unusual or excessive noise or vibration when the fan motors are running. The air flow alarm of 10,000 cfm was selected to ensure that the temperatures in the diesel generator control room will stay below the maximum of 122 degrees F maximum.

The system is automatically started by a thermostat when the temperature in

- the nietel Generator Control Room equals or exceeds 110 degrees F.

Proposed Amendment No. 147 4-92

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . ______ _ _n _ _ _ _ _

p -- _ _ - _ _ _ _ _ _ _ _

cos. PA NT _ ,l

[EAlllpYMrj J RANCHO SECO UNIT 1 IfdiNds/D

" ' " " l TECHNICAL SPECIFICATIONS d TABLE OF CONTENTS (Continued) l l SfLc_t_ toll Pace 3.14.5 Fire Hose Stations 3-57 3.14.6 Fire Barrier Penetration Fire Seals 3-58 3.15 RADI0 ACTIVE LIOUID EFFLUENT INSTRUMENTATION 3-60 .-

'~

I 3.16 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 3-63 3.17 L10VID EFFLUENTS 3-70 3.17.1 Concentration 3-70 3.17.2 Don 3-71 3.17.3 Liouid Holduo Tanks 3-72 3.18 GASEOUS EFFLUENTS 3-73 3.18.1 Dose Rate 3-73 3.18.2 Noble Gases. 3-74 3.18.3 Iodine-131. Tritium and Radionuclides in Particulate Form 3-75 3.19 GASEOUS RADWASTE TREATMENT 3-78 3.20 GAS STORAGE TANKS 3-79 3.21 SOLID RADI0 ACTIVE WASTES 3-80 3.22 RADIOLOGICAL ENVIRONMENTAL MONITORING 3-81 4

3.23 LAND USE CENSUS 3-87 3.24 EXPLOSIVE GAS MIXTURE 3-89 3.25 FUEL CYCLE DOSE 3-90 3.26 LNTERLABORATORY COMPARISON PROGRAM 3-92

.J 147- 3.27 MCLEAR SERVICE ELECTRICAL BUI.LDING._fMERGENCY HEATING 3-93 A_ND AIR CQNQITIONING 3.28 101 DIESELSENERATOR CONTROL ROOM ESSfNTI AL 3-94 VENTILATION SYSIEM 1

Proposed Amendment No. 147 iv

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS TABLE OF CONTENTS (Continued)

Satilon EAge 4.26 RADIOLOGICAL ENVIRONMENTAL MONITORING 4-83 4.27 LAND USE CERSjlS 4-86 4.28 EXPLOSIVE GAS MIXTURE 4-87 4.29 FUEL CYCLE DOSE 4-89 4.30 INTERLABORATORY COMPARISON PROGRAM SURVEILLANCE REQUIREMENT 4-90 4.31 RUCLEAR SERVICE ELECTRICAL BUILDING EMERGENCY HEATING 4-91 VENTILATION AND AIR _ CONDITIONING 147- 4.32 TDI DIESEL GENERATOR CONTROL ROOM ESSENTIAL 4-92

- VENTILATION SYSTEM 5 DESIGN FEATURES 5-1 5.1 SlTE 5-1 5.2 CONTAINMENT 5-2

\

5.2.1 Eggitor Buildina 5-2 s 5.2.2 Reactor Bu11dina Isolation System 5-3 5.3 REACTOR 5-4 5.3.1 Reactor Core 5-4 5.3.2 Reactor Coolant System 5-4 5.4 NEH AND SPENT FUEL STORAGE FACILITIES 5-6 5.4.1 New FutL_lningttion and Temocrary Storage Rack 5-6 5.4.2 New and Spent Fuel Storace Racks and Failed 5-6 Fuel' Storage Container Rack j 5.4.3 Ngw_3nd Spent Fuel Temoorary Storaag 5-6 !

5.4.4 Spent Fuel Pool and Storace Rask Desian 5-6 t

i Proposed Amendment No. 147 vii 1

u ,

RANCHO SECO UNIT 1- '

TECHNICAL' SPECIFICATIONS' q 4:' . LIST OF TABLES Dhle wg 2.3-1 REACTOR PROTECTION SYSTEM TRIP SETTING LIMITS 2-9

-3.5.1-1 INSTRUMENTS OPERATING CONDITIONS 3-27

- 3.5.5-1 ACCIDENT MONITORING INSTRUMENTATION OPERABILITY REQUIREMENTS '3-38b-

3. 6 SAFETY FEATURES CONTAINMENT ISOLATION VALVES 3-40 3.7-1 VOLTAGE PROTECTION SYSTEM RILAY TRIP VALUES- 41a 3.7-2. VOLTAGE PROTECTION SYSTEM LIMITING CONDITIONS 3-41b 3.12-1 SAFETY ~RELATED HYDRAULIC SNUBBERS- 3-51a-e 3.14-1~ FIRE DETECTION. INSTRUMENTS FOR SAFETY SYSTEMS 3-55 3.14-2 INSIDE BUILDING FIRE HOSE STATIONS 3-57a 3.15-1 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 3-61 3.16-1 RADI0 ACTIVE GASES EFFLUENT. MONITORING INSTRUMENTATION 3-64 3.22-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 3-83 3.22-2 REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS 3-86 IN ENVIRONMENTAL SAMPLES 4 .~ 1 -1 INSTRUMENT SURVEILLANCE REQUIREMENTS 4-3 4.1 MINIMUM EQUIPMENT TEST FREQUENCY 4-8 4.1-3 MINIMUM SAMPLING FREQUENCY 4-9

%' 4.2-1 CAPSULE ASSEMBLY HITHDRAHAL SCHEDULE AT DAVIS-BESSE 1 4-12b 147- .4,6-1 DIESEL GENERATOR TEST SCHEDULE 4-35d

+- 4.6-2 ADDITIONAL RELIABILITY ACTIONS %3[

4-42 4.10-1 ENVIRONMENTAL RADIATION MONITORING PROGRAM

4.10-2 0PERATIONAL ENVIRONMENTAL RADIATION HONITORING PROGRAM 4-22a 4.14-1 DESIGNATED SAFETY'RELATED HYDRAULIC SNUBBERS FUNCTIONALLY 4-47d,e TESTED ONLY.AS REQUIRED SY THE SNUBBER SEAL REPLACEMENT PROGRAM 4.17-1 MINIMUM NUMBER OF STEAM GENERATORS TO BE INSPECTED 4-56 DURING INSERVICE INSPECTION 4.17-2A STEAM GENERATOR TUBE INSPECTION 4-57 4.17-2B STEAMGENERATORTUBIINSPECTION(SPECIALLIMIfEDAREA) 4-57a 4.17-3 OTSG AUXILIARY FEEDWATER HEATER SURVEILLANCE 4-57b,c 4.19-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 4-64 SURVEILLANCE REQUIREMENTS 4.20-1 RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION 4-66 SURVEILLANCE REQUIREMENTS Proposed Amendment No. 147 ix

- - - - - _ _ _ _ - = - . _ .

Y; RANCHO SECO UNIT 1 TECHNICAL' SPECIFICATIONS-r Limiting Conditions for Operation u

1.- Reactor Coolant Loop (A) and its associated steam generator -

and at least one associated reactor coolant pump,

~2. Reactor Coolant Loop (B) and its associated steam generator and at least one associated reactor coolant pump,

3. ' Decay'H, eat Removal Loop (A) 3

4. Decay Heat Removal loop (B)

With less than the above required coolant loops OPERABLE, immediately. initiate-corrective action' to return the required coolant loops to OPERABLE status as soon as possible; be .in COLD' SHUTDOWN within 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months .

3.1.1.6 Reactor Coolant System High Point Vents A. The. vent path on Loop A and vent path on Loop B shall be

. operable and closed during power operation.

B. The vent path on the pressurizer shall be operabl'e and closed during power operation.

C. With oneiof the above reactor coolant system vent paths

' inoperable, STARTUP and/or POWER OPERATION may continue

-provided the inoperable vent path .is maintained closed with e power removed from the valve actuator of all the valves in the-inoperable vent path; restore the. inoperable vent path to OPERABLE status within 30 days. If the status is not restored to operable in 30 days, be in HOT STANDBY within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

-D. With two or more of the above reactor coolant . system vent paths inoperable; maintain the inoperable vent paths closed with i power removed from the valve actuators of all the valves in the l inoperable vent paths, and restore.at least (two) of the vent- ,

paths to OPERABLE status within 72.hcurs. If the status is not restored to operable in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , be in HOT STANDBY within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and'in COLD SHUTDOHN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

147~

3.1.1,7 The pressurizer shall be OPERABLE, except when the reactor is in COLD SHUTDOWN, with 3 groups of heaters in two separate banks that are capable of being powered by the diesel. generator trains. With the heaters in one bank non-OPERABLE, either restore the bank to OPERABLE status withinb days or be in at least HOT STAhDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and i PkOT SHUTDOWN within the following 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

l Hith the heaters in both banks non-0PERABLE, either restore one bank ,

1 I

to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in at least HOT STANDBY l within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following l

- 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . J i

Proposed Amendment No. 147 3-2 L - - - . - _ . - - - - - . __________________J

Rc ,.

m IM RANCHO SECO UNIT 1 I, >' TECHNICAL SPECIFICATIONS p

Limiting Conditions for Operation p DAtei .

L A reactor coolant pump or decay heat' removal pump is required to be.in operation before the boron concentration is reduced.by dilution with makeup water. _ ' Either pump will provide mixing which will prevent.. sudden positive reactivity changes caused by dilute coolant reaching the reactor. One decay-

'L

-heat removal pump will circulate the equivalent of the, reactor coolant system volume in one half hour or less. (1)

The decay heat removal system suction piping'is designed for 300 F and 300 psig; thus, the system can remove decay heat when the reactor coolant-system is below this temperature. (2) (3)

One pressurizer code safety valve is capable' of preventing overpressurization when the reactor is ~not critical since its relieving capacity is greater than that requi' red by the sum of the.available heat sources which are pump energy, pressurizer heaters, and reactor decay heat. (4) Both pressurizer code safety valves are required to be in service prior to criticality to conform to the system design relief. capabilities. The code safety valves prevent overpressure for rod withdrawal accidents. (5) The pressurizer code safety valve lift set point shall be set at 2500 psig e 1 percent allowance for error and each valve shall be capable of relieving 345,000 lb/hr of saturated steam at a pressure not greater than 3 percent above the set pressure.

The.electromatic relief valve setpoint was established to prevent operation of the. Safety Valves during transients.

h Two pump operation is limited until further ECCS analysis is performed.

When TAV is below 280*F, a single reactor coolant loop or DHR loop provides sufficient heat removal capability for removing decay heat; but single failure considerations require at least two loops be OPERABLE. Thus, if the reactor coolant loops are not OPERABLE, this specification requires two DHR loops to be OPERABLE, lne purpose of the high point vents is to vent noncondensible gases from the RCS which may inhibit core cooling during natural circulation. In compliance with 10CFR50 Appendix R the power to all the valve actuators in the vent path has been removed.

147-- There are 3 groups of heaters in bank 2, and 3 groups of heaters in bank 3 that are capable of being powered by the diesel generator. Each set of the 3 groups of heaters has a nominal rating of 126 kw which provides assurance that these heaters can be energized during a loss of offsite power condition to maintain natural circulation at HOT SHUTDOWN.

Proposed Amendment No. 147 3-2a

RANCHO SECO UNIT 1 l- TECHNICAL SPECIFICATIONS f Limiting Conditions for Operation REFERENCES (1) FSAR Tables 9.5-2, 4.2-1, 4.2-2, 4.2-4, 4.2-5, 4.2-6 (2) FSAR paragraph 9.5.2.2 and 10.2.2 (3) FSAR paragraph 4.2.5 (4) FSAR paragraph 4.3.8.4 and 4.2.4 (5) FSAR paragraph 4.3.6 and 14.1.2.2.3

'\

d l

l l

l I

i j

Proposed Amendment No. 147 3-2b

. _ _ _ _ . ______-__a

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation i i;

3.7 AUXILIARY ELECTRICAL SYSTEMS h $Y 3.7.1 The reactor shall not be brought critical unless the following conditions are met:

M.

twtG HNAMT 147- A. At least two 220 KV lines are in service.

B. Theswitchyardvoltageisd21$KV_orabove.

l C. Both startup transformers, No. I and No.2, are in service.

D. Nuclear services 4160V buses 4A, 4A2, 4B, and 482 are operb: 's.

E. Nuclear services 480V buses 3A, 3A2, 3B, 3B2, 2A1, 2B1, 2A3, 2B3, 2A4, and 2B4 are operable.

F. Two separate and independent diesel generator trains (train A is both diese,1 generators A and A2, train B is both diesel generators B and B2) are operable each with:

0 1. Separate day tanks containing a minimum volume of 65 percent of tank capacity (265 gallons) of fuel for each A and B and 50 percent of tank capacity (315 gallons) of fuel for A2 and B2. I

2. A separate fuel storage system containing a minimum useable volume of 35,000 gallons of fuel for each A and B and 42,000 gallons of fuel for each A2 and B2. ;

l

3. A separate fuel transfer pump for each engine of a train. j G. Nuclect Service batteries BA, BB, BC, BD, BA2, BB2, BCT., and BD2, which supply vital 125 volt DC buses SOA, SOB, SOC, 50), SOA2, l SOB 2, SOC 2, and S002 are charged and in service. I H. Each vital 125 volt DC buses SOA, SOC, SOB, 500, SOA2, SOB 2, SOC 2, and S002 shall have its normal battery charger aligned to it.

I. 'NuclearfserviceinvertersiSlA2,\S182, SIC 2,andSlD2Dand?staticn

switches 1HSTA3,1H8YB3~,: H8TC3, and H8TD3'are' operable 'for 120-volt' ACivitalcbusfpower.

Proposed Amendment No. 147 3-41

i RANCHO SECO UNIT 1 t TECHNICAL SPECIFICATIONS Limiting Conditions for Operation

-..,n -mym - amwv, n 4E7).2MdMg as wwmmmvmemnpymcwywwww;thodoj wwwblAjasE tcab unless; alt of ),mj.:

pgMw,,J QRww.a E MC NASU $ A-147- tyjA]p{ g g j{ k M h M M 3 d c e ;- M-dSTNS gu-._ _saa,L5 3.7.2.A At least two 220 KV lines shall be in-service.*

< ggaM3f W -

u --_ -nwr (g.Wjhe ym1WRWW3M9*VQssemmwrnoeK'Y'; M L M HOMS ,

BL@iiEl Should all but one 220 KV line be removed from service

[# within I hour tt140perab,ilj,ty,pf_the,gemainjpgJPJ KV line shall be demonstratedbyestaning*iacceptableLresults;Qofperforming survei11ance reqili?ihients 4~.'61~.'A~siiB~a't~leist once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter.

49 4

ifP' within 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months sh-tainingsacceptab1(ggpultsiffo emmerwwwwmsp,wy.y.,m(performing surveillance requirement 4.6.3.A.4.

If at least two 220 KV lines are not in service within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , the reactor

n. ,

shall be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

i l

Proposed Amendment No. 147 3-41a

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation

'147- 3.7.2 TM artisettsNed.' aMhh5h[d @ M M uuwwA 62f l ,, sQ All .b '

gr g MEEniWiUGEMETE . _ ,

Y v, t + r u h . .c

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'k bk kNEMM5N1@2)

=mme TNmEsluEiercema L W mJ

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3. Y ht s %gl.g.< h Mg . . .g:yy;Ag.,

'k_;.y g_.u;. 'x gly ey 4 < 7 '.% .

. .y; t ' ~._ e,; . g w a -...: s:: a : w s _ :. x e 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months the operability oftQenttwo220KVlines i

g;> Hithincir a%%41al.,fitifijifab1EftpstitWjy a

{f($quitsshallbedemonstratedbyferforming surveillance requifli6E once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter; or the reactor shall be in HOT SHUTDOHN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOHN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

h*Hithin 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months "gbtainYa$ h 3 6 E fiiuffsPaffi $ performing surveillance requirement 4.6".3'.'A'.'4"ind*at16aYt~ once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter; or the reactor shall be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

mnm '

Iftheh (c) STAJUSw[th di ays,j spl gegerAtLis,,nopgestofged PERABLE jp O>dt&KEf thefoondi fEcheltjoqjssiestablis i ' 172[h'ouRframiwhen;fT5 th~e' reattor shafl"6 HOT"$NUTDONN

'Dithlh the hEHTh'61 ifs'ind in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

1 1

l

)

Proposed Amendment No. 147 l 3-41b (

4

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation

, , --m JsERin?.cdtical;unlestaQt 3.7.2 ~

erveevnenemmmmwnne,gM7 -md;; elJg-(nomy 147-k;w

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YEb en mwwwwwmM**???%'"*?mmm7s~~nn MM -I ,e Ms n mNegiEglsssi e m m @lR21anW3 8822 d e114 e%0PERABLEld d M 3 ,

y Ane n"'w$y y 3 ,

.- whumaaa%,,.eJ

{ M,,-

S. ,n i M~ m r mblRIEE mmm BPERATIONS$

m ~ n n m $ An

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f[$y hat 4 1., J. j . .

, 4% 3.) /."s .:yp >

2%[ ;,

.' ;p%;1 n w.sisu d. n s aa a a w ;agg Q" . A W WW ' ~

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ljje W1eBSt?q e i A p p #.. wp v . -

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'r 7r Y n ato10PERABLE w~. z t p. r4

~+ .. u . EEP condit%nt.w&4Ysst ~hed s P A d"** M E h d h m -u d l }

Proposed Amendment No. 147 3-41c -

____________- ___-.-___ J

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation

'147- 3.7.2 NN temegN19*5t@-

s k 5515 k$b[N b b $ b E fthb Eik N Specification C. At least two 220KV lines and both diesel generator trains (i.e.,

GEA/GEA2 and GEB/GEB2) shall be OPERABLE.

bk L615iKiaMM!*MM gisJLang Should all but one 220 KV line and one diesel generator train both become hVwithin 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months the by%%ilig be demonstrated operability of the remaining iedptabliThissltiTfr #

220@KV lin performing surveillance requirW5iM5I1:A;*and"atleast 6fiEe per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereaftar,

h": within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months the diesel _ generator.mtrain shall

^ '

e demonstrated to erforming be OPERABt,E by{bbtilat 4 ];accleptably ' ~

7.,6.3.A.4.

3 surveillance..ha~gulfemt ifiglNif.s_re lD_60ti-eperfti.rms.k.~s

- e

. -__. .aug

?itiready wun.-

If either the 220 KV line or the diesel generator train is not restored to OPERABLE status within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , the reactor shall be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

With the diesel generator train restored to OPERABLE status within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , follow 3.7.2.A. With the 220 KV line restored to service within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , follow 3.7.2.B.

l

)

Proposed Amendment No. 147 3-41d

- _-----_--________J

L.

I l

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation

- m*w 9 "

l 7j *

Q3Q*[}Qf:q -

sare;:sattsfied '

, un - ~ as a u w n nu u d.

bbk D. At least two 220 KV lines shall be in-service.

'* wittVW ulacinaxys2QW1_ __

M g h k1 M L E RATI %

EMII Should all 220 KV lines become Q }

(h within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months the opera shall be demonstrated b.

.he'two diesel generator trains erformin,gJyrve llance requir e n t. 4,, . 6,,3..

um .

A ,4, .

ga _.

asjgelajea,f Jhsjh!y1lgg If at least one 220 KV line is not returned to service in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , the reactor rhall be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

\

Hith one off-site circuit restcred to service within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , follow 3.7.2.A.

d i

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l l

l Proposed Amendment No. 147 3-41e i

_j

64 RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation m, n ,m, ,,

147- 3.7.2 [ w w. m m erw cdtu ~ica J nj, essialk n - m ( feee70]. lqow ng ].

_ , _ _ fn ....-. .

isQ

^""l%a gg*gggggggy kM sse$

i Ale Mg m y gg W..h. . ,

gmywm$

_ $?

& $$ , ._ ,. - t. ,

~,-- - - L'l . _ . . - - - . . - _ . ,a, _ ,n w) amm (Y*a.

. Hithin 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months the operability of at least two 220 KV lines circuits shall be demonstrated by $ f5 Min" fiftprDerforming surveillance req}u17einbbt"g'TiddtpMisIFss5T 4T.'ltA!'*6f*th's"rERtc r

%allie in HOT SHUTDOHN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN wjthin the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

performing 6 /SP 9 Within s u rv e i l24 l a n hoursc e r e q uk $ D E! 6'.T.^A".W"a i r eidiW'4 5 fM IEndFeisifi ~ a t*Te aEfti(t s once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter; or the reactor shall be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

y ~~ .

y ,

ge 3 (y

%f al ter! rs kild SHUTDOWNTilhin .

Hs$ibfBD1ty

'Hekt"6'" hours andthTTeicf6EiEill'S5'ih*

in COLD SHUTDOWN within HOT'the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

{l 7- f$g se td jhourl. .. _

h 'emain1Jginonh0RERABLEicondit) s x-nll

{sc .

aaa ns - -- - - --

&Ld6;%5EaM:tL6 Proposed Amendment No. 147 3-41f I

- - )

9 RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation I

'147- 3.7.2 '

wan\

g o W n..

vt g ggggggyfsfisCEMEE5tiWi yen,yggmMgw,

- ] g%yEj??p?p'TUPRQyjyyrynrgp;cy.w* l n_d$

i 1 i gg,~.__"cg3 i a 1 3.

4.

w k emn-,

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. . . .. . . _ _ ~+ a %w#?w? 7MN8"n N"**wipwwwn3 '

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Proposed Amendment No. 147 I 3-41g 1

l I L-____-_.______ _ l

4 RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation

] 147- 3.7.2 M j,((rA( M k hj[ nE M fk)$ [t5E5 [ lid {i NIAIiT6116iEI7difb$55$ 7 gguKementsiarelsatisfiedP '

wn-wm gi eM.,nw~fication2f F. Both startup transformers shall be in-service.

7AbbifEANIIIE[3E7 w, 4 -

f3gjjh.,,.ne,w, mratenw..w.n--vwgough1POWERLOPERATIONS fXcffbE!!7 s_ ;_.. -

y .

Should one startup transformer become My Mm,RABLEff ,.

a. withinIhourtheoperabilityofatleasttwo220KVlinesshall be demonstrated bylobfaiMhi'ficcip*ti61sRidlisPffdm7 performing surveillance 4.6.1.*A';"Ed'Et leht 6hEF^pdr'8"houff"thereaf ter.

b. demonstrated Within8hoursthe,Aleselgeneraton. trainsu_shall,_be,lerforming tab'lerres'ltdfrom surveillance requiriihhn{T48.'3. A.

to be OPERABLE jre@ifeiEd S by gbtaining'accep'4.ijililGUhd TNnninF@{Juu.a.w.f^hallMtibejperjrme{on;dfe(eljgen If startup transformer no. 1 is not restored to OPERABLE status within

! 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , the reactor shall be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 205 hours0.00237 days 0.0569 hours 3.38955e-4 weeks 7.80025e-5 months .

If startup transformer no. 2 is not restored to OPERABLE status within ,

48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , the reactor shall be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months l

- and in COLD SHUTDOWN within the following 205 hours0.00237 days 0.0569 hours 3.38955e-4 weeks 7.80025e-5 months . j l

Proposed Amendment No. 147 3-41h

_ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ ._ _. i

t RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS

(-

Limiting Conditions for Operation emn-m.- n, i n.

. ., n nn -n~w v.

147- 3.7.2 gj,i Jr,,7-. c ~ l ~a -unl i.c.a ~ ~es- sx a. ~~

~l lsofi,i. k,,e _f ,i n..ng oll,o,~w .,.j.i g g 7c_ri.f

~..-asuaj . .,

s, a ,,-~.-a, -

[ $

G. Both startup transformers are OPERA 3LE.

gWeiS55($it]

. . - ymme~nnn->+.. ,

m,E. POWER;0PERAIIONSE,F w n. -

yswx**M*?t$MJQ Q uD .,,, n .i If both startup transformers become .__

a. within one hour take action to place the reactor in HOT SHUTD0HN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 205 hours0.00237 days 0.0569 hours 3.38955e-4 weeks 7.80025e-5 months .

\

4 v.

i 1

)

\

Proposed Amendment No. 147 3-411

)

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation

- * " ?

147~ 3'7*2

~

""s'""

"ee"n*fn* Lid"t'{"cah'Q, "o "lQi"ng J Js"iAlf"0fst"kd"l 7 .g 3.g a m aiaauu.w.aaa f N$b5$

H. Nuclear service buses as listed in 3.7.1.D and 3.7.1.E shall be OPERABLE.

% $$N meP3GERIEGEifem3 tag!gN1 Should one nuclear service bus become for greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ,

(( the reactor shall be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

rm -u~ee wmmm>~~wv.nm?.

If hanton nuclear service bus foe; . _. f tra i as listed ri"D.T.D and 3.7.1.E should become ,,_g, ~ ~

(' within one hour take action to place the reactor in HOT SHUTD0HN within.the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following

- 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

l l

Proposed Amendment No. 147 3-41j l- _ _ -

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation n,

.f ram ~~r mn-3.7.2

~

147- :

rg- f~criti._icMisifeTf.EWiffWe"T,_fif,a_ilifMP

~ omm a .om _. m T_pAk$hk'h$h&?

~ mbeltichtionf8

""~ {

i I. Nuclear service batteries as listed in 3.7.1.G shall be charged and in-service.

DM!Nbk '

u m f! B EiRi s iair @ ii W @ 7 t!EiiB7 Should one' nuclear service battery become " M ({for greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , T h the reactor in COLD shall bewithin SHUTDOWN in HOTthe following SHUTDOHN 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months If more than one nuclear service battery as listed in 3.7.1.G should become' @ g

-h) within one, hour take action to place the reactor in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

0!

i t

I Proposed Amendment No. 147 3-41k

RANCHO SECO UNIT 1

. TECHNICAL SPECIFICATIONS Limiting Conditions for Operation

' I N I D A ? b ! M 3 8 0 1,1 @ 5 f 5 f7

f 1.

,D,ggjigg.

w ._-._J J. Nuclear service battery chargers as listed in 3.7.1.H shall be

. OPERABLE.

Q W 155!$

ta y g sy sigeserwsica n to w Should one nuclear service battery have no battery charger for greater l than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , !

ThthereactorshallbeinHOTSHUTDOWNwithinthenext6hoursand in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

If a standby charger is aligned in place of its normal charger for greater than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months (A,'$' the reactor shall be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

! If more than one nuclear service battery has no battery charger as listed in 3.7.1.H, i yh within one hour take action to place the reactor in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the,following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . .)

i Proposed Amendment No. 147 3-411 ;

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation nw,w n

'I.shalknotiirema

,n-,,ernen,einicrjtjen-,>an, ipyfMe o--- .fo~lh...

~e-a- ief,w,J

'147- 3.7.2 .

+ en1]Anlessfal tw

r,,ggggg,,

unwaa m ua 1W, M 7g,t,T,m,%__I".e. .a_(M_ik. W_._@, m_sYa'.a,_dittit1C,w .m m Se aag ttchesyng Specification

3. 7. 2. :- Nuclear service inverters and static switches as listed in 3.7.1.I shall be OPERABLE.

!I3

' g 19f!INE Nil!Nf M l"J!!8 33 ctaun essumw g Should one inverter or static switch become }forgreater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ,

a. the reactor shall be in HOT SHUTD0HN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 'and

- in COLD SHUTD0HN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

\

IE Proposed Amendment No. 147 3-41m

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS i Limiting Conditions for Operation 147- 3.7.2 s iTkf@is#WWastisfledW Psgutra '^~""""kdi6EiilINIYMIIIIcytiits1?unl

" " " " ~ ~ " " " " " es

! u m uw w w a n x a s.a u de f3 W!f1%il6DiifrTiM.-[{ElEdGEiWdilISfati wanews,mmw ~ - ~~-x-mesmwwwaagc3 Ski tithes sev ink $$f 3.7.2.K.NAstaticswitchshallnotbealignedtothebackupsource in' place of an OPERABLE nuclear service inverter except during switching periods.

{iMlEE5I555I{$ ee-y-, _ . . . .

. n-e-

$7A RTU

, L %g w ehlf~0 ER;0PERATI0llS

_.m..,,a1 E. .*

m 4 TActik)-

w.-

If more than one nuclear service inverter or static switch as listed in 3.7.1.I should become non.4P_ERAB&.n.,

aw w A within one hour take action to place the reactor in HOT SHUTDOHN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOHN within the

- following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

\

Proposed Amendment No. 147 3-41n

______-____-_-_______-a

I RANCHO SECO UNIT 1 l TECHNICAL SPECIFICATIONS Limiting Conditions for Operation

~ O'I' ~ -

w=srauw 4_m L. The switchyard voltage is at least'219KV.

$b[ $2[$d GnMM5iiiGedWGHf5 IGD PPet.UnE3fW

b. -

Shouldtheswitchyard'voltagedropbelow'2]fKV,

[*g, positive actions, within the District's procedures, will be implemented in an attempt to return the voltage to at least'2194 i KV. ,

If the switchyard voltage goes below 219?KV, i

(8), both diesel gener ton, trains shalkbe demonstrated.0PERABLE within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months by tainingiadeeptablisresult surveill ance requ rement 4.6.3. A'.'4'.***"'""*~~hfroisjherformi n

~^"~"~~

Should the switchyard voltage not be restored above 219 KV within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , (W

A the reactor shall be in HOT SHUTOOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and

- in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

l Proposed Amendment No. 147 3-41o

l I

l .

RANCHO SECO UNIT 1

[,

TECHNICAL SPECIFICATIONS I

Limiting Conditions for Operation l

147- 3.7.3 The voltage protection system trip setting shall be as stated in Table 3.7-1.

3.7.4 Voltage Protection System Limiting Conditions A. STARTUP and POWER OPERATION are not permitted unless the minimum requirements and action statements of Table 3.7-2 are met.

l B. In the event the number of protective channels falls below that' l listed in Table 3.7-2, the plant will be brought to a HOT '

SHUTDOWN within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

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Proposed Amendment No. 147 3-42

i RANCHO SECO UNIT 1 I TECHNICAL SPECIFICATIONS Limiting Conditions for Operation Ralei The auxiliary electrical power systems are arranged so that no single failure can inactivate enough safety features equipment to jeopardize plant safety.

The normal source of power to the redundant nuclear service loads is by the two startup transformers to connect the 220-KV station switchyard. All of the 147- normal power supply to plant auxiliary loads can be provided through the two unit auxiliary trar.sformers connected to the generator buses. Emergency power for the nuclear service loads is obtained from two on-site diesel generator trains (train A is both diesel generators A and A2, train B is both diesel

- generators B and B2). Since the startup transformers are sized to carry full plant auxiliary loads, if plant auxiliaries' power is not available from the unit auxiliary transformer, it will be obtained from the startup transformers.

The five 220-KV transmission lines are not under the direct control of the Rancho Seco station. Therefore, all five cannot be assumed to available at all times. However, extensive reliability and protective features are utilized so that the probability of losing more than one source of 220-KV power from faults is low. By requiring that two 220-KV lines are in service prior to startup, one circuit will be immediately available following a loss of the onsite alternating current diesel power supplies and the other offsite 220-KV line. If there is a loss of all 220-KV remote connections, power to the safety features wil] be supplied by the diesel generator trains. The 35,000 gallons of fuel stored in each storage tank permit operation of the ,

147- diesel generators A and B for seven days. The 42,000 gallons of fuel stored l in each storage tank permit operation of the diesel generators A2 and 82 for ,

- seven days. It is considered unlikely not to be able to secure fuel oil from an outside source during this time under the worst of weather conditions. ;

l 147- The set of eight 125 volt DC control buses (SOA, SOB, SOC, S0D, SOA2,

- S082, SOC 2, and SOD 2) are arranged so that loss of one bus will not preclude safe shutdown or operation of safety features systems. During periods when i one plant battery is de-energized for test or maintenance, the associated 125 volt DC bus can be supplied from its battery charger.

l l

1 1

Proposed Amendment No. 147 3-42a

r RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS

+:-TABLE?3:7Alr, ~,* *

+s- y - ,

o , ,. . . . . .

. ,....-~m- .-- ..e. >...m .

J,.m, mVOLTAGE. PROT...E.CTIO. N LSYSTEM' RELAYoTRIP) VALOES @ + 'r

~ '

EQUIVALENTS . . * ? TIME DELAYr*

'Td160: BUS; VOLTS $ # $ OlS'ECONDS)' NOTES 51"- '

nUNDE,RV0ijAd.R d_i EE5_YSM. Ni.'." '

m

~ VOLTSF e #D $ " "

( x s s C5 y

.{ :

147- Yh??Diffniti?'a

^'

" Time? Delay 1 ,. . _ . <

~ .c... . . ,

,;TriplSetNPointe .7, 3771;2038i . E5.0 iz :,0. 52

" ' "~

6(Drop >10uth .s g; -

54,'1 ff=f 't4 s 7a%- -'@^

^13771?*738?,

p BMISersee.,

l'[4 N/A2 _i

? Time;Delayt . y

-?TF1pTSet Poi ^nt .

$(Dropout)KL

70 Percent of, Set Poistf' ug;, e < - .. - _

4

'i2640L zi27] ^"l 7 3.0;* 0.5; a

[e ty-.q3 ,#- ,-i , 44 . + q , . , ,

c ., _ - ~

NOTES 1AForbu'ttrippi_ng,1anladditional'O.'515e'cond. tim'e? delay lmustlbDdded.u>#

g ,s -m . vs. -

y 3 r w m m-:p w ~ ~ , n+wnn .mn' w:', w m ? ,

1 l

l Proposed Amendment No. 147 3-42b a____-___-__

147a i

! RANCHO SECO UNIT'l TECHNICAL SPECIFICATIONS

'\

, , , . . .- m

-TABLE 13';7-2 7(Note'lT' ,~, , i

, ..t ymy m ,

me a g e "P", ? Total.y. w ; ;No.gof:n . ,., .

,(Minimum- :1" g ;y ,

Relays /dg P fdnctionala

" Unit; j ~ Q%r! Number:ofd YChannels; a'4 gp'Channell, WTo Trip),4 TChannels;y.gyChannels}

1: Operable; n, If( .

,{ '- .,, .l 4

'q j .

I g fgi 'l--

' ^

) ..O g f

, fAE ' J w

2/ Bus > a: :

147%:. ,.cU n d"e/*'*[rvoltage; s -3/ Bust-. w2

2i 4. _

l

.I

......w.

QACTION'_ STATEMENTS.. . ,"

Ac ti on A '-:O Hi th : thelumtie r 80PERABi.EMhaiinsi s Jone : 1~ess~than"thestotal:

~

G ' ~

v -

NumberToftChannels (fol lowi ng ^condi s are satisfied:' ti on$opefationimayfproceed ? ' ~

e a.mThe"Inop;elrable'Ch'anniljiDiacedl1d theltHpped conditionwithin ~~ ' " "'

ion'ethour.~s !

-y

, .....q ,:pa -.<

, l. ( f-r r, 6 . , , , . e,1p-. g ,, , 7,....,

d' tb;f>?iThelNinimum Channels;0PERABLELrequi._ rrement,:is met;f however,;one' a"

~ ,.fadditionalfchannel ..maymbe,. bypassed:for.up toL2 hoursiforl' -

isurveillan~ce' testing . . . ..

< No.tec luThe' table"isino, tlaphlihableluhen~theLplant31s11n'~ cold shutdown, -,

s

; . s -

l Proposed Amendment No. 147 3-42c

RANCHO SEC0 UNZT 1 TECHNICAL SPECIFICATIONS <

Limiting Conditions for Operation 147- Each redundant pair ("A" and ".C"s. B" and "D".)I of > the eightc125. volt DC control . buses 1(SOA and , SOC,5 SOB:and SOD, .SOA2 and SOC 2, and > S002 and S002)'

has. a standby. battery charger in. addition to its normal battery charger. On-the: loss of power from one battery charger:per pairtthe standbyibattery charger -isiputEinL service. However, the7 standby charge can beJalignedi ini place'ofilts normal; charger forLonly: 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .because the standby'.61ttery; charge is powered from a!differentldieseligenerator-than the normal battery ,

, charger. .There: arelpotential ~ interactions after 2' hours 7thaticouldioccur.

.upon.the loss-of-off-siteipoweriand'a single: diesel generatorifailure. .iThis

. situation hasLnot been analyred but by limiting the' time thi's: configuration t

could exi's t, the probabilitycof occurence .is sufficiently lowf to" justify._

- limited ' operation ~ in this condition.

During periods of station operation under the condition of electrical system degradation, as described above in Specification 3.7.2, the operating action required is to start and run suf ficient standby power supplies so as not to compromise the safety of the plant. As seen in Specification 3.7.2, a time limit is placed on operation during certain degraded conditions based on the ,

reliability of the available power supply. i 147- 'FourLneclearTservice inverters (SlA2, S182, S1C?, and S102h and static, switches.(H8TA3,'H8TB3, H8TC3, and H8TD3);are required to be.cperabl.a.to ,

' power the_120Lvolt AC vital. buses. The nuclear. service inverters are powered from' diesel generators 1A2 and 82 and the static switches are powered from diesel lgeneraturs-'A and'B.. This design ensures that upon loss of'an inverter

~

'or 'a' single. diesel generator; the- 120 volt, AC. Vital buses will : continue to receive power 'and. that- there are no" system . interactions. .One nuclear service

'iriverter or static switch is permitted to be inoperable for up' to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

The static' switch is"only used. as.a backup for the inverter. It is not permitted to belused when an inverter.is' operable:except"for switching' period becauselit < receives power from the' nuclear service 480V buses and there is no

' battery backup available.

Tne voltage protection ~ system is designed-to isolate the nuclear service buses from the startup transformers before the voltage drops below the allowable operating limit of' the,. equipment. The undervoltage protection for the 4160: volt nuclear service buses is 3771 2 38 volts. This' corresponds to a. nominal: switchyard voltage range of 219 KV.

REFERENCE FSAR, Section 8 1

1 l

Proposed Amendment No. 147 l 3-43 '

~

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation Table 3.14-1 (Continued)

FIRE DETECTION INSTRUMENTS FOR SAFETY SYSTEMS Minimum Operable Zone Instrument Location Heat Flame Smoke

~75-1 B Switchgear Room (NSEB) 0 0 .1 75-2 BB2 Battery Room (NSEB) 0 0 1 75-3 BD2 Battery Room (NSEB) 0 0 1 76-1 A Switchgear Room (NSEB) 0 0 1 75.2 BA2 Battery Room (NSEB) 0 0 1

. h. 3 -BC2 Battery Room (NSEB) 0 0 1

.77-1 North B Electrical Equipment Room (NSEB) 0 0 1 77-2~ South B Electrical Equipment Room (NSEB) 0 0 1

'78-1 North A Electrical Equipment Room (NSEB) 0 0 1 78-2 South A Electrical Equipment Room (NSEB) 0 0 1 81 B Cable Tunnel / Shaft (NSEB) 0 0 3' 32 A Cable Tunnel /Shatt (NSEB) 0 0 3 N B Hechanical Equipment Room (NSEB) 0 0 1 84-3 A$phanjpalEqui,mentRoom(NSEB) 0 0 1 b$5I dn l

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Proposed Amendment No. 147 3-55a ;

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_ - - _ - - _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ __ J

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" RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.14.3 Sorav and Sprinkler Systems Specification 3.14.3.1 The spray and/or sprinkler systems located in the following areas shall be OPERABLE:

a. Control Room (Zone 3)

b. Controlled Area, Mezzanine Level (Zone 20)

c. Main tube Oil Area, Grade Level (Zone 32) 1 d. Grade Level (Zone 34)

e. North Diesel Room (Zone 40)

f. South Diesel Room (Zone 41)

g. West Controlled Area, Grade Level (Zone 42)

h. East Controlled Area, Grade Level (Zone 43)

1. South and Eest -20' Level (Zone 46)

j. NSEB B Cable Tunnel / Shaft (Zone 81)

k. NSES A Cable Tunnel / Shaft (Zone 82)

1. NSEB Mechanical Equipment Rooms A and B (Zone 84) 147QQ(($$ % %h"M%Q q@HEsi3hme$4 T

% eda 2Ciss.i MA:uG u m@db & @~ W jzene 3.14.3.2 Hith one or more of the above, items a through f, required spray

, and/or sprinkler systems are inoperable, within one hour establish a continuous fire watch with backup fire suppression equipment for those areas in which redundant systems or components required to safely shut down and cool down the plant could be damaged; for other areas, establish an hourly fire watch patrol. Restore the system to OPERABLE status within 14 days or, in lieu of any other report required by Specification 6.9, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.5.E within the next 30 days outlining the action taken, the caur,e of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

3.14.4 CO2 System Speci fication 3.14.4.1 The CO2 systems located in the following areas shall be OPERABLE j with a minimum capacity o_f 66 and a minimum pressure of 275 psig in the storage tank: -

a. Zone 12 Hest DC Control Room Hezzanine Level i

b. Zone 13 West 480 VAC Room Mezzanine Level I

c. Zone 14 West Cable Tray Area

d. Zone 15 East Cable Tray Area !

e. Zone 16 East 480 VAC Room Mezzanine Level ]

f. Zone 17 East DC Control Room Mezzanine Level I

g. Zone 36 Hest Battery Room Grade Level Proposed Amendment No. 147 3-56 1

mm ' "t RANCHO SECO UNIT'l TfCR; CAL SPECIFICATIONS

' Limiting Conditions for Operation

-Table 3.14-2 (Continued) p INSIDE BUILDING FIRE HOSE STATIONS ID No. Location.

147- III Diesel Generator Building Hose Stations FPHS-D-001' Train'A Engine Room Elevation O'-

FPHS-D-002 Train A' Control: Room Elevation O' FPHS-D-003 ' Train A Mezzanine Elevation 18'6" fPHS-D-004 Train B Engine Room Elevation O' FPHS-D-005 Train B Control Room Elevation O'

~

FPHS-D-006 Train B Mezzanine Elevation 18'6"

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- Proposed Amendment No. 147 3-57b

147-RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.27 Nuclear Service Electrical Building Emeraency Heatina Ventilation and Air Conditioning System Specification 3.27.1 Both Nuclear Service Electrical Building Emergency Heating

. Ventilation and Air Conditioning trains shall be OPERABLE.

et E31 p g g j l@ild$5EdIsid?$ $ AIi8E d ate Tfh Hith one Nuclear Service Electrical Buildin Emerc ency Heating Ventilation and Air Conditioning trainftics $, restore the train to OPERABLE status within 7 days"6Ftrin at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b gi'g' HithbothNuclearServiceElectricalBuljdingEmerg cy Heating W Ventilation and Air Conditioning trains 1 Q. restore the trains to OPERABLE status within 3.6 dayi"6 Fbi n at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

BAiR1 The Nuclear Service Electrical Building (NSEB) Emergency Heating Ventilation and Air Conditioning System is required to provide cooling

- to protect required electrical components in the NSEB.

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Proposed Amendment No. 147 3-93

RANCHO SECO UNIT 1 h TECHNICAL SPECIFICATIONS L Limiting Conditions for Operation 147- 3.2.8 TDI Diesel Generator Control Room Essential Ventilation System specification

.. , _ mmwwmvmmwve~w~m i 3.28.1 -,m,nne-eyjospeJssentiahVentil4tiefdn Generatojr g etrol hjj waama-waaasub callMBEa VM. t:W- "f G. ER'0PERATI- - - 4

' k N II yh' Hith one TDI Diesel" Generator _ Control Room Essential Ventilationtrainleon~wrtTdEQ,demonstratetheoperabilityof the remaining traini " RETthfb theisnes4]PERABE train to OPERABLE status within 3 days or bf9h"at"lefst HOT SHUTDOWN within six hours and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

Hith both TDI Diesel Generator Control Room Essential (Vtih Ventilation trains [iisiPDPERA8(E, restore at least one peli' train to"0PERABLf status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in u 1tt'least" SHUTDOWN within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within t e following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . With onefnes@PERABLS train restored to OPERABLE status, continue with"AbtionT'above i using the time the remainingWeiliML condition was established as the start of ttie't' COP"""

Bases The TDI Diesel Generator. Control Room Essential Ventilation System is required to maintain the temperature in the control room below 122*F

- to protect required electrical components.

Proposed Amendment No. 147 3-93a

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. RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards TABLE 4.1-1 (Continued)-

INSTRUMENT SURVEILLANCE REQUIREMENTS-Channel Description Check Test Calibrate Remarks

57. Voltage Protectjon 3,,

's 147* a. Oidh_l.tjage o

'w5etpoint;.jAs (( hs "

-h R e b.F Onderwh15$g elRelay % 7%Wy R

. ew,y,yw.m

.~.

. - n]

sw. -

58. Containment Area High 5 M(1) R (1) Test using installed source Range Monitor

59. Wide Range Containment M N/A' R Water Level 60, Containment Hydrogen S M Q Analyzer

61. Emergency Sump Level M N/A R

62. Containment Wide range H, N/A R Pressure Monitor / Recorder

63. ' High Range Noble Gas S M- R Effluent Monitors.

- RB Exhaust Stack'

- Aux. Building Stack

- Radwaste Vent

64. Main Steam Line Radiation S M(1) R (1) Test using installed source Moni tors

65. Subcooling Margin Monitors M N/A R i

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66. Incore Thermocouple M N/A R

.67. Low Temperature Over N/A (1) R (1) Prior to cooldown Pressure Protection S = Each shift M = Morithly P = Prior to each startup if not done previous week 0 - Daily Q = Quarterly R = Once during the refueling interval W = Weekly SY = Semiinnual I

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1 Proposed Amendment No. 147 4-7c 1

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards

2. The test will be considered satisfactory if control board indication verifies that all components have responded to the actuation signal and the appropriate breakers shall have completed their travel.

3. Additionally it shall be verified that the NSCH flow through each operating cooler exceeds 1400 gpm and air flow through the cooler exceeds 40,000 cfm.

l 4.5.2.2 Comoonent Tests A. Testing At least quarterly, Inservice testing of Reactor Building Spray pumps and valves shall be performed in accordance with Section XI of the ASHE Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.5ba(g), except where specific written relief has been granted by the NRC pursuant to 10 CFR 50, Section 50.55a(g)(6)(i).

B. Flow Path Verification Following Inservice testing of pumps and valves as required by par'agraph 4.5.2.2.A, required flow paths shall be demonstrated operable by verifying that each valve (manual, f power-actuated or automatic) in the flow path that is not locked in position is in its normal operating position.

Positions of locked valves shall be verified in accordance with the provision of Section XI of the ASME Boiler and Pressure Vessel Code.

147- C. The pressurizer shall be tested as follows:

1. The pressurizer water level shall be determined to be within its limits at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . !

2. The power supply for the nuclear service backed pressurizer heaters shall be demonstrated OPERABLE at i least once per refueling interval by using the Nuclear ]

- Service Bus to energize the heaters. '

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l Proposed Amendment No. 147 4-30

- , RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards.

Baiel The Reactor Building emergency cooling systems and Reactor Building spray system are designed to remove the heat in the containment atmosphg preventthebuildingpressurefromexceedingthedesignpressure.t{gto /.

The delivery capability of one Reactor Building spray pump at a time can be tested by opening the valves in the line from the borated water storage tank, opening the corresponding valve in the test line, and starting the corresponding pump. Pump discharge pressure and flow indication demonstrate performance.

With the pumps shutdown and the borated water storage tank outlet valves closed, the Reactor Building spray injection valves can each be opened and.

closed by operator action. With the Reactor Building spray inlet valves closed, air can be blown through the test connections of the Reactor Building spray nozzles to demonstrate that the flow paths are open.

The equipment, piping, valves, and instrumentation of the Reactor Building emergency cooling system are arranged so that they can be visually inspected. The cooling units and associated piping are located outside the secondary concrete shield. Personnel can enter the Reactor Building during_

power operations to inspect and maintain this equipment. The nuclear service cooling water piping and valves outside the Reactor Building are inspectable

\

at all times.

s" 147- The operability of the nuclear service bus backed pressurizer heaters is

- demonstrated by energizing the heaters once per refueling interval.

REFERENCES (1) FSAR, section 9.

l Proposed Amendment No. 147 4-31

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 4.6- EMERGENCY POWER SYSTEM PERIODIC TESTING

- Specification

~147- 4.6.1 Offsite Power Sources A. .Each of the 220 KV lines required by 3.7.1.A shall be:

Determined OPERABLE at least weekly by verifying correct breaker alignments and indicated power availability, and B. Each Start-up Transformer required in 3.7.1.C shall be demonstrated OPERABLE at least once per REFUELING interval by transferring nuclear service buses as listed in 3.7.1.D from the normal startup transformer supply circuit to the alternate startup transformer supply circuit.

-i gy;MBini~56dii5is

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Proposed Amendment No. 147 4-34 L - - _ _ - - _ _ _ - _ _ _ _ _

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 147- '4.6 Emergency Power System Periodic Testing (Continued)

Specifications 4.6.2 Nuclear service ~ buses required by 3.7.1.0 and 3.7.1.E shall be determined to be OPERABLE at least weekly by verifying cor rect breaker alignment and indicated power availability.

[b$

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'g,NM[ kip 555}dS

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l Proposed Amendment No. 147 4-34a

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 1

147-- . .

4.6 Emergency Power System Periodic Testing (Continued)

$NA O Yd D b $$p geesmil useas Specifications ed fy'ing;that Each diesel. generator both diesel generatorstrain shall in the trainbearedemonstrated OPERABLEOPERABLE %Med! _b ,,y$4E8/ ens M R f_.

A. In accordance'with the frequency specified in Table 4.6-1 by:

'I . Verifying the fuel level in the day tank,

2. Verifying the fuel level in the fuel storage tank, 3.* Verifying the fuel transfer pump starts and transfers fuel from the storage system to the day tank,

4. Verifying.the diesel starts from a manual signal and accelerates to a. nominal 900 rpm for A and B and a nominal 450 rpm for A2 and

82. The generator voltage and frequency shall be 4160 ( 420) j 9: volts and 60 (11 2) Hz after the start signal. (Note 1) 5.*

Verifyit2550Tand?2750'kw between for A and B and?3000:andf3300?kw for A2ng] 1

. and 82 for^at" lent #

60 minutes ,(Nete 1). "" " ~ """

6.fgh Verifying the diesel generator is aligned to provide emergency power to the nuclear service buses at the conclusion of the test.

g 6 g*e:3 7 $ 3 h ri N D Wii Q i N M tbi7

$$UEE[(finafthtp~"*tioneitaeHabig"ty TkIrm 1stemust naaw -

gifidaMeMM&

Note 1 iAllf planned? engine" starts"may be' preceded-byransengine'prelube periodG Nith( the? exception? ofionce ' peril _84 Jays";f all.l;pla~nned, enginetstarts;mayibe: preceded;by' warmup;preceduresLrecommended by

,theimanufacturervandLaaylalso^1ncludelslosstartingJand gra<.ual~ s loadingssotthat mechanicalfstressTand wearsonitheldiesel' engine 5is minimizedN ThedestingEperformedlonce~ every)1841 days shalls include if astestarting:(lessithaniorrequait to110iseccids): ~

u um

~

^

Surveillance shall not be performed when a diesel generator train or startup transformer is not operable in accordance with TS3.7.2.

Proposed Amendment No. 147 ,

4-34b l

L h RANCHO SECO UNIT 1 b . TECHNICAL SPECIFICATIONS Surveillance Standards i

! :147--

B. Fuel'011 Storage

.~,m

1. tBy_n g .;remov- ngta.ccu.

- mm.e mula. ted wat.er.

,y&-

,n-mnw,vnw

'a)h M.,. n , e : , m m e w mFromithe:dayltankPatileast monthly:and/afterleachy%

"' iici:aiioniwhenitheidie,se1[isloperatedifor, greater) ithanLlihour an .w.-~> -Rand Qa wnv.cn.~,--mm~mwn ~m i,bM_F_om,1, a

r -t ihe...storageltankiatileastimonthly@pp -

~

p fY~l"$7 M H"?1*T y f'J{f3Q** [ f $ @@F

~

7 /A?!W, , yjs' p M? g'ap-

2. ( ify t'po11@.E_accordanceLwith

_r_io.r2toladdit..i_onit.h. thet. s orage:

.?;;f,y,,,:

t m- - - -~ - -

i' Tank,s

% -.- and: y.

_ _ _..~ ._ ~ .~.

a)Q"

" By, ver

_.ify._.ingi

,. ~in -accordancei wi th,vthe,: t_ests _spe. .( c i fl ed 14 ASIN 0975--81Fpriorkto;additionLtolthelstorage ~~ ^

!tanksithatfthehamplelhas:r

% 4.aua.m --

1) M An"absoluteispecificegravityTat[60/60*Fiof7

% greaterithanLor equalito-0;83ibut<1'essithin or

?equalito:0 90ior!-an1 API gravity!ati60*FJof igreaterqthan;or:(equaPto'26'degpeekbutLl'ess -

than or equal?tol38Ldegrees

\

f_ ~.- ASTM 01298-77s* " ' ""lin;accordance ~ " " " * " " " " ~with 9

ii) g'5" (InestiDiscosityTatT40*C7off^grsatirT than' e 4 edualtto"4110 cen':1WawardavhnitLy scosity,

,(SUj;atL1.00'F) m y p osti MJ 4 ibutilessJthanormeuasto140;1; measured ND ii3cS ,i.ordance1with _ _

_ . .~ - , -

. v.e m p~ w . ,m,. n - n., ,,

1 1 1 ),(.A;.; flash

- t o' ,.- ,,,,, n ..or) greater,j, than))25* F,l.f e v.sa ~,and u lpointAqualg_y m._, m . _ _

iv) !Water

. _-~ ,and rm m sed ,i men t of,l e s,.. s th.._ an oriequa.. , ,.m_l -- to lf

"~" ^ ~

- 9 0.05spercentibyJyolbmel W ~ ^

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Proposed Amendment No. 147 4-35

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RANCHO SECO UNIT 1-TECHNICAL SPECIFICATIONS Surveillance Standards 147 b) f5/ vertfying;withinc3hdaystof-obtaining theesample 7 that >the ; other:fproperti es lspeci fi ed [i n (Tabl o pASTM0975L811aremet;when{testedcinaccorda nceiwith ;

4 ASTM; D975-81 dexcept?that;: theianalysi s. for/ sul fur,

~

pmay!be?performedtin accordance;ivithiASTM,0.1552379 H

teor?a A.STM

+ - D2622-421

- - - L(Note"2)?

3. rAtiliesiFMONTHLYJ byro btai n'i ngWsampl e' oft fuel coi i Tfrom "then::~storagel:tanksiinfaccordance with2ASTMcD4057-814 Y p (1981 E and; verifying thatftotaliparticulate:L i,,, z, .

'.1contami nati on ;i s t.. l es s t than110! ag/ l i terfwhere checked li n EfaccordancetwithASTM;D2276473M1978)),tMethod1A:

Note 2 If one or more properties are out of specification, within 62 days of obtaining the bad fuel oil, verify that an additional sample of -

fuel oil from the fuel oil storage tank is within specification, gr empty and refill the tank with a new shipment of fuel oil

- within 77 days of the original out-of-specification se.mple.

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4 Proposed Amendment No. 147 4-35a

, . RANCHO SECO UNIT 1

[ TECHNICAL SPECIFICATIONS Surveillance Standards

.-,a,wn :.wn: ::w vnw 147- C. (At teach? refuel i ng ai ntersal ,i.by: ',

, gen;mmwe mw w 1 Die,se1LGenerator: Inspections" 3' ,

a)

{S'06jstf(?

insp i n J accordance ; wi th' procedures : prep inicection onj unction : wi ttdthe l mai ntenanc( recommendati on s tq rovidediby?itsiman0facturernfor"this p classTof'

4tandbylservice; a2e'

b) the"di esel;- generators : A23 and / B2::t67an s.

Subjectingi.'in i'spection n accordance withlproceduresyprepared in . conjunction [wi th[t'he' maintenance?and J .D sg surveillance;p_rogras? recommended 2bylthelJOI Owners C"Gro'up?i ni"Desigm Revi sion ?and J)uali ty; Revalidati on -

Report lfori.RanchM Se.c'o [ Appendix y & * ;

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1 Proposed Amendment No. 147 4-35b i

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS l

Surveillance Standards ,

! 147- 2. Simulating a loss of off-site power in conjunction with I c a. safety features' actuation signhl','._(Note 54MNoteT6)fand!

x s g -

a) Verifying de-energization of the nuclear service buses and operation of the load shedding circuitry.

b) Verifying the diesel starts on the auto-start isignal:(Note'3)',< energizes,the ndclear service? ?

buses 7 verifying ' proper' operation" of the automatic load sequencing circuitry, and operates for greater than or equal to 5 minutes in this condition.

After energization, the steady sthte voltage and frequency of the emergency buses shall be maintained at 4160 ( 420) volts and 60 ( l.2) Hz during this test.

- 3. Simulating a loss of off-site power and verifying that on interruption of the emergency power sources the loads ;

are shed from the nuclear services huses in accordance with design requirements and that subsequent loading of the emergency power sources is through the automatic load sequencing circuitry. The diesel generator will be (operated 1for atileast' 5 min 6teslin this -conditiona (Npejl)N ~

147- 4. Verifying the diesel generator operates for at least 24 ,

mhou'rs (Note 1)] During the? first 2[ hours ofLthisitest.;

the~ diesel" (jenerator "shall' be' loaded 'between"2650 and 2850 kw for A and B and 3000 and 3300 kw for A2 and B2 M and for the remaining 22 hours2.546296e-4 days 0.00611 hours 3.637566e-5 weeks 8.371e-6 months of this test, the diesel generator shall be loaded between 2550 and 2750kw for A and B and 3000 and 3300kw for A2 and B2.

Note 1 All planned engine starts may be preceded by an engine prelube

( period.L ' Hith 'the' exception 20f once.per 184-days,~ all* planned _ ;

engine: starts'may be' preceded.by: warmup pro _ceuures, recommended by the manufacturer and.may also include slow starting'and gradual' loading so that mechanical stress and_ wear .on the: diesel engine is

' minimized; The testing performed once every 184 days.shall-includefaststarting(lessthanorequalto10 seconds).;

Note 3 All planned engine starts for the purpose of this surveillance testing may be preceded by an engine prelube period. The testing 147- shall include fast starting (less than or equal to 10 seconds).

Note 4 Prior to the performance of this Mst the diesel generators shall be operated at between 2550 and 2750 kw for A and B and 3000 and 3300 kw for A2 and B2 for at least I hour and until engine operating temperatures have stabilized.

Note 6 When thu test required by specification 4.6.3.E is performed, then the test required by specification 4.6.3.C.2 is not required to be performed.

- Proposed Amendment No. 147 4-35c

l RANCH 0 SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 147- D. At least once per 10 years,.by, starting all four diesel generators simultaneously [(Note-3) and verifying that they l

accelerate to a nominal 900 fpm for A and B and a nominal 450 i rpm for A2 and 82 within 10 seconds after the start signal.

The generator voltage and frequency shall be 4160 (1420) volts and 60 ( 1.2) Hz within 10.0 seconds after the start signal.

(

E. tat least':once"per40 yearsi simul'atingla loss of off-sit'e.-

lower;in conjunctirsn withia simulated SFAS;(Note 5), and-

y_ _

.5 A- - - > > '

1. Verifying de-energization of the nuclear service buses and load shedding from the nuclear service buses.

2. Verifying the diesel starts on thel auto-startfsignal. 9 energizes the' nuclear service buses with' permanently, connected 11oads,: loads lthrough,the load: sequencer and operates lfor greater than or equal lto 5 minutes while

~

its; generator is loaded with the emergency' loads. - After energization, the steady state voltage and frequency of the< emergency buses shall be maintained'at 4160 ( 420)

~ volts and.60.( 1.2).Hz during this. test.

3. Ve.rifying for the A and B diesel generators that all automatic diesel generator trips, except engine overspeed, ground fault and generator differential, and 3

verifying for the diesel generators A2 and B2 that all automatic diesel generator trips, except engine overspeed, low lube oil pressure and generator differential, are automatically bypassed with an SFAS.

Note 3 i:Alll plannsd engineistarthforMe..pu'rpose ofYthd survelliance-testing may be preceded by.an engine:prelube,per:iodT .The Ltesting '

shall include fast starting (less than or : equals to' 10~ seconds).

Note 5 ? All plAnnbEengine starts fohtid' purpose 'of thisisurveillance.

(testing may be_ preceded 'byian engine. prelube.' period., ,The testing

_shall. include fast starting.(in"less than or.iequal:to 10 seconds)

.and: fastfloading- through ~ theisequencer; ,

Proposed Amendment No. 147 4-35d

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards-1; W M 26!3-147- 4.6.4 Batteries in the 125 volt DC systems shall be tested as follows:

A. The voltage and specific gravity of each pilot cell shall'be-measured and recorded weekly.

B. The specific gravity, level and voltage of each cell shall be measured and recorded every month.

C. Each time data are recorded, new data shall be compared with old to detect signs of deterioration.

D. During each refueling interval,'the battery shall be subjected to a rated load or equivalent test. The battery 1 voltage as a function of time shall be monitored to establish that the battery performs as expected.

, * - aemhalitwns hie,'w siwa4J-k&$$bh

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1 Proposed Amendment 147 4-35e

RANCHO SECO UNIT 1' TECHNICAL SPECIFICATIONS Surveillance Standards h191 147- The operability of the 220KV lines, the nuclear service 4160V buses, and the nuclear service 480V buses are demonstrated by verifying correct breaker alignments and indicated power availability. Surveillance 4.6.1.B can only be performed during a refueling shutdown when both diesel generator trains are operable or the core is flooded to 37 feet to ensure the required decay ,

- heat removal capability is available. (

The tests specified are designed to demonstrate that the diesel generators will provide power for operation of safety features equipment. They also assure that the emergency generator control system and the control systems for the safety features equipment will function automatically in the event of a loss of all normal a-c station service power, and upon receipt of a safety features actuation signal. The testing frequency specified is intended to identify before it can result in a system failure. The fuel oil supply, starting circuits and controls are continuously monitored and any faults are alarmed and indicated. An abnormal condition in these systems would be signaled without having to place the diesel generators on test.

1474 The limiting of the maximum load on the TDI diesel generators A2 and B2 to less than the qualified load of 3300 kw provides assurance that the crankshafts will stay within the proven limits for high-cycle fatigue cracks.

(Dissel __ generators 1 A2 aAd B2' will be loaded during' surveillance testing "between ~3000 Land 3300;KHlwhich provides~ assurance that the' qualified load of ,

3300.KW will not be exceeded.

At least once per 10 years a diesel generator test will be performed simulating a loss of off-site power in conjunction with a simulated SFAS and loading of actual loads to the maximum extent possible without damaging plant systems (i.e., use of recirculation flow or manual valving out a system to protect plant components).

1 Precipitous failure of the plant battery is extreu.aly unlikely. The surveillance specified is that which has been demonstrated over the years to l provide an indication of a cell becoming unserviceable long before it fails. {

REFERENCE (1) IEEE 308 ;

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l Proposed Amendment No. 147 4-35f l 1

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4 RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS

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Surveillance Standards 147- .ELECTRICPOWERSYSTEMI Table 4.6 DIESEL GENERATOR TEST SCHEDUL1

-Number of failure ~1n:

Last-20 Valid Tests

Test Freauency gg @5AYNEAE)DITHLffI?

Qj rAthleast*WEEKL Q 2r:

ucasaw ~ ~

\

N

Criteria for determining number of failures and number of valid tests shall be in accordance with Regulatory Position C.2.e of Regulatory Guide 1.108, Revision 1, August 1977, where the number of tests and failures is determined on a per diesel generator basis. For the purposes of this test schedule, only' valid tests conducted after the license amendment issuance date shall be included in the computation of the "last 20 valid tests."

- This test frequency shall be maintained until seven consecutive failure !

free demands have been performed and-the number of failures in the last 20 valid demands has been reduced to one or less.

1 1

Proposed Amendment No. 147 4-35g ;

__ _ _ _____ = .

y y

I RANCHO SECO UNIT'1 TECHNICAL SPECIFICATIONS Surveillance Standards 147 -

TABLE 4.6 3 ADDITIONAL' RELIABILITY ACTIONS n . --w :,,, n, C No,,,,n..,n mmnyn a ofifai. lures a s NO A,ofifailu.res" "

mjintlast?20 $ T'" 7 'sinilastii100 W I L -

GalidJtest** . ~$ valid 6testsi G i k Action ., _ i_. 9 ' ,

v 7 , m ~<mn w~~

bs05g usam6had& A thin;114, aysipreparetand maintain *a -

,TS. wvmwgxmemrvn:wwwmmn~W1 P report 6for!NRCraudit.. describing)the

{djeselfgeneratorreli~abilityV improvementrprogram? implemented?at (the ssi te .2 Mi nimum : requi remen tKfo r ltheXreport are;indi'catediin" Note 117to "

{this LtableME** ^"" ~ # "

UG f u 5j"s. "m$wu F T " E S 11a"m P " *"? W"~y g Perforara y equalificationstest5,d, rogramif6tithelaffacted!#jeseli

' generatorMRequalifidationttest q program t requi rements fa re ti ndi ca ted i n .

Note >2;to"this(table M h if

_\

yq ,

f' #

% i'

% p%1,4 ye,* ,p $ p,, . ,

Q Fori the:. purposes of Tthis0 schedule? only;valld;.testU conddcted af ter y' the.flicens.e: amendmentrissuance: datelshal1 ~ b'e s' included sin ;thef /

,icomputatio~nfof f ;au thei"I~ast 20jyalidItests" andi"last 100ivali'd"testsi"3 7>

Proposed Amendment No. 141 4-35h

(

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards

- 147-NOTE 1 TO TABLE 4.6-2 REPORTING REQUIREMENT nn. e m nen - nnn,,__ _ -. - wn m --n.-_-

Asta1 minimum;the;AeDabilityilmprovement; Program,;repor.tifor NRCjauditishal1

'fncludea e , w- w- ~~ mmv; v, raitummaryiofn1C,,.nn n -v~. u ~! invalid)ithatsoccurre;d sithin'.the time testsd(validiand taE"rperiod?overlwhjchStt p -,aa - ~l .

eilasti20/100lvalid~ i.ww.-

tests'wererperformed.

, b)Manalysi rof(fai l urss"a6d JefifsfiahWiffro6t"caus e s Tof;unu.afai l u re xs am- ~~u nu.~~ ~ - - - - ~

,m, iw m v rq%WWYTMB?'M YYQ9pn w ~ v~

c)Wevaluationisfdeac'hof?the:recommendationvof;NUREG/CR4660! Enhancement

'*of Onsitel Emergency 01eselhGeneratoriRn11abilitytin1'0peratinggReactors," ""~'" ^

withLrespect"to/their,capp~lication www aua .- +

to the Plant d) ,. i d e n ti fi ca tion e of r al l racti onsi taken 3661 7tiiEhk'E5Ifd(DR6Ffec t~ the'

%Etoot!causesiof!failuresidefinedlin;b) abo' vel ~and 2)?a'chiese;~ aigeneral

{mprovementlofidi ss eligeneratorf rel i abi l i tj nmn. ,

e) m6.e i t. n..- n ~ - - - m a n n e ns chedul ei forii mpl ementati onioficachl ac ti o_ni_from 'd) 7abov e

W 3 "

f) -Vansassessment

.em.wwW(MiWN#bND7fWrDYDDDMFMU of TW W"l ect r"i c;&? ;1E etexisting: reliability;of4e < %. . md.

cpower?to

~

"e n'gi neered-safety-festu pefejui pme{]g d

Once ra511 censeelhasTprepared ? and : mai ntai n an s i ni tial ~ report .d etai l i ng ,t.he m #

Tj_diese1SgeneratorYpeliabilitylimpfovementfprogramiatihis sitenas%definedia a f ter6eachl fai l ure duri ng ?alval i d fdemand Mfor 1so il ong asi the iaffec ted i di es el generatorj uni tJ conti nue sn toyviol ate l the? cH teri al(3 /20 L ore 6/100)2 fdr>the % i re l i abi 11 ty?i mprosementirogFami remedi al l ac ti on Q Th'el s uppl emental deport C y needionlygpdateitheCf.a11 pre /demandLhistoryiforctheraffected! diesel; generator unit 31nce theMistLreport;for;thatldiesel;generatoUTheis'upplementat W repoEFsha11;also determination Rif?present?antanalysis;offthe!

possib1'e,and0sha117delineat'eLany?further? failure (s)Nwith;atroot procedural;_causef hardwsre?orloperationalschangesito.beLincorporatediintolthe? site diesel 1

{

generatorEimprovement? program'andethe" schedule;forcimplementatib'7of n those cha_ng@g i;'V

- - -. w r # 1 , _ _ _ ,

)

]

IInvaddition"tolthel_a66 ,eA v submitTaiyearly; data, ,reportion the" diesel: generator Ireliabi]ity/ p F " "

~

Proposed Amendment No. 147.

4-351

p- I I- RANCHO SECO, UNIT.1 TECHNICAL SPECIFICATIONS Surveillance Standards NOTE 2' TO TABLE 4.6-2 DIESEL GENERATOR REOUALIFICATION PROGRAM

_ _ ~ ~ m m . _ s m e e m m e % ~ .~

forelsevenaconsecubversuccessfu1(demands;withoU7Uatfailu_re 7-- '

within (1)

' *gPe(dayt/oftdteselygepefitoribeingirestoredJtofoperab1's(statbijrdm~the i30i jiastifa11ereiand!fourtseniconsecuti vei saccessfel fdemands f wi thout i a

- 147-- 5fdaysiofidiesels eneratoribeingWestoredito::opeFable '

'pfailsreDwithin9)wameStitusifr6mithe,1astAfai10re?'*g*"""QWskM

~ -n-

.. - -ne-am-nwmmm

( 2 ) hgI f; oneffai l ure ~ occurs: duri ng ythe seven3 ifi rst r,ywmmyGR, id, , ,~ -

tests

'requal l'fi cati on s testirograafi perfofm Iseven y sacces s fulidemandbi thou t

. 147* an addi tionalf fai lure: wi thi n; 30i dayil ofi dieseU geniratoE bei ng .

f'res;~toredFto#erable7statusi aftef(ithe (fitst ifailure100 l the r'egsalification1testVprogramMadfourteesiconsehutiveisuccessi ,

1 fdemands?withoutlaifailure(withini757daysfofsbeing1 restored!tooperable

!s tatus "af wwsterithe;uif fit!fai l u re ~ofJ thel requalixfi cati on ? test~1 prog swxuwdmunaww w ram.

wn, y n m mnvrucwe~ w m @PM (3) RIfeone;fa11ure;occursiduringtthe!s sieRWW"v'vw, econdise enitest ~E,(te..stsi83through3m 714)? ofM 1 )$aboveh perfors kfourteen /consecuti veisuc ce s's fu12 deman'd svuA

'wi thouft an inddi tional$ fal l ure %1 thi n; 75 r daysi ofa the{"fai l u re whi ch oc c u_rre_d w~ (duri ngsthe frequal i fi cati oni= te s ti ng FA (4) g"Fol lowi ngIthe Tap 66MfailliF4Tdsfihj7tdiTe qNii fiiihEtistTprogram declardthe7diesekgeneratordinoperablesndifollo'sthe{ w applicable" feguirements of4 Specification 33.7;2MTheldles'elfgeneratorsshalltnot s ibescon'sideredfoperablFsntitthediese'1 hoqualifiedM8"*""""~"^^ ~ ~ "[generatob~hasPsuc'cessfa119 ~

"- ~ " "

n- ~~ nnnn~--n . - . .

(5). Duri n g;requa l i fi catiIo~nitesti n+g~Lthes dieseb . generator; shoul d 't not: bej 147~- (#tpted"m6re? frequently!thaniat24-hour 11ntervais q 3 ~

w > c m-mn. - - -n.~

.AfterTs.7di .-- alniast eselogenra or beenMuccessfully> requalifiedWsubsequentQ'

<ropeatedfrequailifisati6nktestsLwi,11"not be' required"for"that~ diesel" generatorn underitheIfollowing; conditions:

eou; ww~~ '

147 -

(a) The'n0mtisdfi

% # ~ M1ure's71"nWell,i_iR20ivalid@6_gts f

---1 .-

a inleE~than'5'.Y

- <- ~ _ m c, 147- (b) ' T_hT.6um_6WE.Niib7es3.Id. ~fhi_llisti100Evalid ti,ityml'sTlessegthan

, ,, g x11,% -

(c) InithereventSthat"followingssuccessfuGeiju'alification ofca7 diesel _

generatoMtheinumberiofafai l uresii sTs ti.11ni n Lex ce s sfof s they remed i a.1]

actionictiterias(a"and/ordbiabove)ithelfollowing exception!will' be" '

allowedintinthejieselfgenerato61s? hot 1ongerAin'v.iolation of the rehediaMaction m;- z criteria'(aiand/orNb>aboVe); ' " 4 4 >u ill?notebes required 1.providsdEf 6KaftfeFsifvalid ? n 147- Qi, g]{NdEd@0resdin?theilast:

l e n'mber3af.ifai1 u 201and/orL100Nalid! tqts?haslott .*

i nc reased Once"the-di esel; generator (inno31ondeNi nNiolatidt bkthe '

remedials actionsrj terialabovekthe -provislow ofu.thoseicriteriaialone ^ ' " ' ~ willa 1 y,y,; gm e r l

j Proposed Amendnent No. 147 4-35j

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards Specification (Continued) 4.10.1 C. 2. (b) Verify that the HEPA filter bank removes 199.9 percent of the D0P when tested in-place in accordance with ANSI N510 while operating the filter train at a flow rate of 3200 cfm 2 10 percent.

D. Started on a manual signal and operated for 15 minutes iri each 31-day period.

Balti The purpose of the Control Room /TSC Emergency Filtering System is to limit the particulate and gaseous fission products and toxic products to which the Control Room area and Technical Support Center would be subjected during an

. accidental radioactive or chemical release in or near the Auxiliary Building. The system is designed with two redundant filter trains each of which consists of a moisture separator, a heater, a high efficiency particulate filter, two banks of charcoal filters, a second high efficiency particulate filter and a booster fan to pressurize the Control Room and Technical Support Center with outside air.

147-~ EBecause this system ist not normally operated, a periodic test is required to insure its operability when needed. Monthly testing of this system will show that the system is available for its designed safety action. During 3 this test the system will be observed for unusual or excessive noise or vibration when the fan motors are running. The flow of 1600 cfm makeup air was selected to limit the maximum radiation dose to occupants of the Control Room /TSC in an accident. For this analysis, both charcoal filter banks were assumed to provide DF's of 10, while the HEPA filter DF is assumed to be 100. The laboratory analysis to show 195 percent removal of methyl radiciodide is necessary to receive credit for a DF of 10.

Refueling interval testing will verify the methyl iodide removal efficiency of the charcoal and the amount of leakage past the charcoal and HEPA filters are at least equal to the design values.

147- The filtering system is automatically started and the normal system isolated ,

when the radiation level or when the Chlorine level increase.

The testing required after painting, fire or chemical release, is not to be j interpreted to include minor touch-up painting, housekeeping chemicals and ;

detergents, or other routine maintenance or housekeeping activities. l l

Proposed Amendment No. 147 '

l 4-41b l

L__ -- i

RANCHO SECO UNIT 1 TECHHICAL SPECIFICATIONS Surveillance Standards 4.31 NUCLEAR SERVICE ELECTRICAL BUILDING EMERGENCY HEATING VENTILATION AND AIR CONDITIONING ,

Specification ,

4.31.1 The NSEB Emergency HVAC shall be demonstrated operable at least once per 31 days by initiating flow through the essential air handling unit and verifying:

1. Verify that the air handling unit maintains a flow rate of 24,500 cfm 10 percent.

2. Verify that the condensing unit is operational.

N O W 1$2h

<edg6Eits$:e B11e1 The purpose of the Emergency Nuclear Service Electrical Building Emergency HVAC is to limit high temperatures which the building would be subjected to upon loss of normal cooling. The high temperatures will affect the environmental qualification of safety related electronic equipment housed within the NSEB which is used to support the Control Room /TSC upon accident 3 conditions. The system is designed with an air handling unit and a condensing unit which are activated upon high temperature signals.

Since this system is not normally operated, a periodic test is required to ensure its operability when needed. Monthly testing of this system will show that the system is available for its safety action. During this test the system will be observed for unusual or excessive noise or vibration when the fan motors are running. The air flow of 24,500 cfm was selected to limit the temperatures in the building to 80*F maximum (with the exception of the cable shafts).

The system is automatically started when the temperature in the NSEB 147* Switchgear Room exceeds 95'F.

1 l

l l

Proposed Amendment No. 147 4-91 4

L_ _ _ _ __ _

(_

147-RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 4.32 IpI DIESFL GENERATOR CONTROL ROOM ESSENTIAL VENTILATION SYSTEM

$p_gci fication 4.32.1 The Diesel Generator Control Room Essential Ventilation System shall j be demonstrated operable at least once per 31 days by initiating flow through the essential air handling unit by verifying that the air handling un.it maintains a flow rate greater than the low flow alarm )

setpoint.

l

{AbolienMiih b 7 D

Dale 1 The purpose of the TOI Diesel Generator Control Room Essential Ventilation System is to limit high temperatures which the local control room would be subjected to upon loss of normal cooling. The high temperatures will affect the environmental qualification of safety related electronic equipment housed within the Diesel Generator Control Room. This Control Room is designed with an air handling unit which is activated upon a high temperature signal.

Since this system is 'not normally operated, a periodic test is required to ensure its operability when needed. Monthly testing of this system will g show that the system is available for its safety action. During this test the system will be observed for unusual or excessive noise or vibration when the fan motors are running. The air flow alarm of 10,000 cfm was selected to ensure that the temperatures in the diesel generator control room will stay below the maximum of 122 degrees F maximum.

The system is automatically started by a thermostat when the temperature in the Diesel Generator Control Room equals or exceeds 110 degrees F.

l l

Procosed Amendment No. 147 4-92

_ _ _ _ _ _ _

v t e Letter Sequence Supplement
TAC:63030, (Approved, Closed)
Initiation Request, Request, Request, Request, Request, Request, Request, Request, Request, Request Acceptance... Supplement, Supplement, Supplement, Supplement Administration Meeting Questions Answers Results Approval, Approval, Approval, Approval, Approval, Approval Other: A11745, Evaluation of DSR-48 Emergency Diesel Generator Crankshafts at Rancho Seco Nuclear Generating Station, ML20126J866, ML20126J973, ML20135E867, ML20149D631, ML20149F003, ML20196E677, ML20196E697, ML20206H162, ML20212B420, ML20214K863, ML20215G661, ML20234C529, ML20234C558, ML20234D524, ML20234D615, ML20234D649, ML20235M565, ML20235Q511, ML20236L543, ML20236N639, ML20236N713, ML20236S088, ML20237B265, ML20237B279
MONTHYEAR1987-12-29 [Table View]

ML20235F530

Text

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