Text

Proposed Tech Specs,Revising Pages 3-6 Through 3-10 & 4-7 Through 4-12 to Upgrade DHR Requirements for Mode 3 W/ Reactor Trip Breakers Closed to Same Requirements That Exist for Modes 1 & 2
	ML13331A928
Person / Time
Site:	San Onofre
Issue date:	04/28/1987
From:	; SOUTHERN CALIFORNIA EDISON CO.
To:	;
Shared Package
ML13331A925	List: ML13331A924; ML13331A926; ML13331A928;
References
	TAC-65271, NUDOCS 8705050389
	Download: ML13331A928 (24)
	v • d • e

ENCLOSURE I Consists of pages numbered 3-6 through 3-10 and 4-7 through 4-12.

8705050389 870428 PDR ADOCK 05000206 P

PDR

ENCLOSURE I 3.1.2 OPERATIONAL COMPONENTS APPLICABILITY:

Applies to the operating status of the reactor coolant system equipment and related equipment. For the applicable surveillance requirements, see Table 4.1.2.

OBJECTIVE:

To identify those conditions of the reactor coolant system necessary to ensure safe reactor operation.

SPECIFICATIONS: A. At least one pressurizer safety valve shall be operable or open when the reactor head is on the vessel, except for hydrostatic tests.

B. The reactor shall not be made critical or maintained critical unless both pressurizer safety valves are operable.

C. During Modes 1 and 2, all three reactor coolant loops and their associated steam generators and reactor coolant pumps shall be in operation. With less than the above required coolant loops in operation, be in at least Hot Standby within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , except as modified by Specification D below.

D. The limitations of Specification C may be suspended during Modes 1 and 2 as follows:

1. Operation may be conducted with 0, 1, 2 or 3 reactor coolant pumps operating during low power physics testing at less than 5% of full power.

2. Whenever reactor power is less than 10% of full power, operation with one or two reactor coolant pumps operating shall be limited to less than 24 consecutive hours.

E. During Mode 3, the following specifications shall apply:

1. At least two of the reactor coolant loops listed below shall be operable:

a. Reactor coolant loop A and its associated steam generator and reactor coolant pump.

b. Reactor coolant loop B and its associated steam generator and reactor coolant pump.

c. Reactor coolant loop C and its associated steam generator and reactor coolant pump.

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2. At least one of the above reactor coolant loops shall be in operation.*

3. With less than the above required reactor coolant loops operable, restore the required loops to operable status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in Hot Shutdown within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4. With no reactor coolant loop in operation, suspend all operations involving a reduction in boron concentration of the reactor coolant system and immediately initiate corrective action to return the required reactor coolant loop to operation.

F. During Mode 4, the following specifications shall apply:

1. At least two of the reactor coolant loops/residual heat removal (RHR) trains listed below shall be operable:

a. Reactor coolant loop A and its associated steam generator and reactor coolant pump.

b. Reactor coolant loop B and its associated steam generator and reactor coolant pump.

c. Reactor coolant loop C and its associated steam generator and reactor coolant pump.

d. Residual heat removal (RHR) pump G-14A and one associated RHR train.

e. Residual heat removal (RHR) pump G-148 and one associated RHR train.

2. At least one of the above loops/trains shall be in operation.**

3. With less than the above required loops/trains operable immediately initiate corrective action to return the required loops/trains to operable status as soon as possible; if the remaining operable loop/train is an RHR train, be in Cold Shutdown within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

All reactor coolant pumps may be de-energized for up to one hour provided (a) no operations are permitted that would cause dilution of the reactor coolant system boron concentration, and (b) core outlet temperature is maintained at least 40oF below saturation temperature.

All reactor coolant pumps and residual heat removal pumps may be de-energized for up to one hour provided (a) no operations are permitted that would cause dilution of the reactor coolant system boron concentration, and (b) core outlet temperature is maintained at least 40oF below saturation temperature.

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4. With no loop or train in operation, suspend all operations involving a reduction in boron concentration of the reactor coolant system and immediately initiate corrective action to return one required loop or train to operation.

G. During Mode 5 with reactor coolant loops filled, the following specifications shall apply:

1. At least one residual heat removal (RHR) train shall be operable and in operation,* and either

a. One additional RHR train shall be operable,** or

b. The secondary side water level of at least two steam generators shall be greater than or equal to 256 inches of narrow range on cold calibrated scale.

2. With less than the above required loops/trains operable, or with less than the required steam generator level, immediately initiate corrective action to return the required loops/trains to operable status or to restore the required level as soon as possible.

3. With no RHR train in operation, suspend all operations involving a reduction in boron concentration of the reactor coolant system and immediately initiate corrective action to return the required RHR train to operation.

H. During Mode 5 with reactor coolant loops not filled, the following specifications shall apply:

1. Two residual heat removal (RHR) trains shall be operable** and at least one RHR train shall be in operation.*

2. With less than the above required RHR trains operable, immediately initiate corrective action to return the required RHR trains to operable status as soon as possible.

The RHR pump may be de-energized for up to one hour provided (a) no operations are permitted that would cause dilution of the reactor coolant system boron concentration, and (b) core outlet temperature is maintained at least 40oF below saturation temperature.

One RHR train may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing, provided the other RHR train is operable and in operation.

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3. With no RHR train in operation, suspend all operations involving a reduction in boron concentration of the reactor coolant system and immediately initiate corrective action to return the required RHR train to operation.

BASIS:

One pressurizer safety valve is sufficient to prevent over pressurizing when the reactor is subcritical, since its relieving capacity is greater than that required by the sum of the available heat sources, i.e., residual heat, pump energy and pressurizer heaters.

Prior to reducing boron concentration by dilution with makeup water either a reactor coolant pump or a residual heat removal pump is specified to be in operation in order to provide effective mixing. During boron injection, the operation of a pump, although desirable, is not essential.

The boron is injected into an inlet leg of the reactor coolant loop.

Thermal circulation which exists whenever there is residual heat in the core and the reactor coolant system is filled and vented, will cause the boron to flow to the core.

Lack of further mixing cannot result in areas of reduced boron concentration within the core.

Prior to criticality the two pressurizer safety relief valves are specified in service in order to conform to the system relief capabilities.(1 )

The plant is designed to have all three reactor coolant loops operational during normal power operation (Modes 1 and 2).

Under these conditions, the DNB ratio will not drop below 1.30 after a loss of flow with a reactor trip.( 2)(3) With one reactor coolant loop not in operation, this specification requires that the plant be in at least Hot Standby within one hour. However, exception is taken whenever reactor power is less than 10% of full power. Heat transfer analyses show that reactor heat equivalent to 8% of full power can be removed with natural circulation only; hence, for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months the specified upper limit of 10% of full power with 1 or 2 reactor coolant pumps operating provides a substantial safety factor.

In modes other than Modes 1 and 2, functional redundancy in the core heat removal methods (not necessarily system redundancy) is specified to satisfy single failure considerations.

Functional redundancy, as applied to the San Onofre Unit 1 power plant, includes use of diverse heat removal methods.

Furthermore, single failure considerations apply only to active components.

In Mode 3, a single reactor coolant loop provides sufficient capability for removing decay heat; however, single failure considerations require that two loops be OPERABLE.

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In Mode 4 and Mode 5 (reactor coolant loops filled), a single reactor coolant loop or RHR train provides sufficient capability for removing decay heat; but single failure considerations require that at least two methods (either RCS loop or RHR train) be OPERABLE.

In Mode 5 (reactor coolant loops not filled), a single RHR train provides sufficient heat removal capability for removing decay heat; but single failure considerations, and the unavailability of any of the steam generators as a heat removing component, require that at least two RHR trains be OPERABLE.

The operation of one reactor coolant pump or one residual heat removal pump provides adequate flow to ensure mixing, prevent stratification and produce gradual reactivity changes during boron concentration reductions in the Reactor Coolant System.

The reactivity change rate associated with boron reduction will, therefore, be within the capability of operator recognition and control.( 4)

References:

(1) Final Engineering Report and Safety Analysis, Sections 9 and 10.

(2) Final Engineering Report and Safety Analysis, Paragraph 10.2.

(3) Supplement No. 1 to Final Engineering Report and Safety Analysis, Section 3, Question 9.

(4) NRC letter dated June 11, 1980, from D. G. Eisenhut to all operating pressurized water reactors.

3-10

TABLE 4.1.2 MINIMUM EQUIPMENT CHECK AND SAMPLING FREQUENCY Check Frequency la. Reactor Coolant 1. Gross Activity At least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

Samples Determination Required during Modes 1, 2, 3, 4, 5 and 6.

2.

Isotopic Analysis 1 per 14 days.

Required for DOSE EQUIVALENT only during Mode 1.

1-131 Concentration

3.

Spectrascopic 1 per 6 months (2) for E (1)

Required only during Determination Mode 1.

4.

Isotopic Analy-a) Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , (3) sis for Iodine whenever the specific Including 1-131, activity exceeds 1-133, and 1-135.

1.0 m Cl/gram DOSE EQUIVALENT 1-131 or 100/ E (1) m Cl/gram.

b)

One sample between 2 and 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months following a THERMAL POWER change exceeding 15 percent of the RATED THERMAL POWER within a one hour period.

5.

Boron concentration Twice/Week (1) E is defined in Section 3.1.1.A.2.

(2) Sample to be taken after a minimum of 2 EFPD and 20 days of POWER OPERATION have elapsed since reactor was last subcritical for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or longer.

(3) Until the specific activity of the reactor coolant system is restored within its limits.

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TABLE 4.1.2 (continued)

Check Frequency l.b Secondary

1. Gross Activity At least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

Coolant Determination Required only during Samples Modes 1, 2, 3 and 4.

2.

Isotopic Analy-a) 1 per 31 days, whenever sis for DOSE the gross activity EQUIVALENT 1-131 determination indicates Concentration iodine concentrations greater than 10% of the allowable limit.

Required only during Modes 1, 2, 3 and 4.

b) 1 per 6 months, whenever the gross activity determination indicates iodine concentrations below 10% of the allow able limit. Required only during Modes 1, 2, 3, and 4.

4-8

TABLE 4.1.2 (continued)

Check Frequency

2. Safety

a. Boron Concentration Monthly when the reactor is Injection critical and prior to return Water Samples of criticality when a period of subcriticality extends the test beyond 1 month

3. Control Rod

a. Verify that all rods At each refueling shutdown Drop move from full out to full in, in less than 2.7 seconds

4.

(Deleted)

5.

Pressurizer

a. Pressure Setpoint At each refueling shutdown Safety Valves

6. Main Steam

a. Pressure Setpoint At each refueling shutdown Safety Valves

7.

Main Steam

a. Test for Operability At each refueling shutdown Power Operated Relief Valves

8.

Trisodium

a. Check for system At each refueling shutdown Phosphate availability as Additive delineated in Technical Speci fication 4.2

9.

Hydrazine

a. Hydrazine concentra-Once every six months when Tank Water tion the reactor is critical and Samples prior to return of critica lity when a period of sub criticality extends the test interval beyond six months

10.

Transfer

a. Verify that the fuse Monthly, when the reactor is Switch No. 7 block for breaker critical and prior to 8-1181 to MCC 1 is returning reactor to criti removed cal when period of subcriti cality extended the test interval beyond one month 4-9

0 TABLE 4.1.2 (continued)

Check Frequency

11.

MOV-LCV-1100 C a. Verify that the fuse Same as Item 10 above Transfer Switch block for either breaker 8-1198 to MCC 1 or breaker 42-12A76 to MCC 2A is removed.

12.

Emergency Siren a. Verify that the fuse Same as Item 10 above Transfer Switch block for either breaker 8-1145 to MCC 1 or breaker 8-1293A to MCC 2 Is removed

13.

Communication

a. Verify that the fuse Same as Item 10 above Power Panel block for either Transfer Switch breaker 8-1195 to MCC 1 or breaker 8-1293B to MCC 2 is removed 14.a. Spent Fuel Pool Verify water level per a. Once every seven days Water Level Technical Specification when spent fuel is being 3.8 stored in the pool.

b. Refueling Pool

b. Within two hours prior Water Level to start of and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter during movement of fuel assemblies or RCC's.

15.

Reactor

a. Per Technical Specifi-

a. Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Coolant Loops!

cations 3.1.2.c and Residual Heat 3.1.2.0, in Mode 1 Removal Loops and Mode 2 verify that all required reactor coolant loops are in operation and circulating reactor coolant.

b. Per Technical Specifi cation 3.1.2.E, in Mode 3 verify 4-10

TABLE 4.1.2 (continued)

Check Frequency

1.

At least two required

1. Once per 7 days reactor coolant pumps are operable with correct breaker align ments and indicated power availability.

2. The steam generators

2. Once per 12 associated with the two hours required reactor coolant pumps are operable with secondary side water level

> 256 inches of narrow range on cold calibrated scale.

3.

At least one reactor

3. Once per 12 coolant loop is in hours operation and circulating reactor coolant.

c.

Per Technical Specification 3.1.2.F, in Mode 4 verify

1.

At least two required

1. Once per 7 days (RC or RHR) pumps are operable with correct breaker alignments and indicated power availability.

2.

The required steam

2. Once per 12 generators are operable hours with secondary side water level > 256 inches of narrow range on cold calibrated scale.

3.

At least one reactor

3. Once per 12 coolant loop/RHR train hours is in operation and circulating reactor coolant.

d.

Per Technical Specifications 3.1.2.G and 3.1.2.H, in Mode 5 verify, as applicable:

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TABLE 4.1.2 (continued)

Check Frequency

1.

At least one RHR train

1. Once per 12 is in operation and hours circulating reactor coolant.

2. When required, one

2. Once per 7 additional RHR train is days operable with correct pump breaker alignments and indicated power availability.

3. When required, the

3. Once per 12 secondary side water level hours of at least two steam generators is > 256 inches of narrow range on cold calibrated scale.

e.

Per Technical Specification

e. Once per 12 3.8.A.3, in Mode 6, with water hours level in refueling pool greater than elevation 40 feet 3 inches, verify that at least one method of decay heat removal is in operation and circulating reactor coolant at a flow rate of at least 400 gpm.

f.

Per Technical Specification 3.8.A.4, in Mode 6, with water level in refueling pool less than elevation 40 feet 3 inches, verify

1.

At least one decay heat

1. Once per 12 removal method is in hours operation and circulating reactor coolant.

2. One additional decay heat

2. Once per 7 removal method is operable days with correct pump breaker alignments and indicated power availability.

4-12

ENCLOSURE II Consists of pages numbered 3-6 through 3-10 and 4-7 through 4-12.

ENCLOSURE II 3.1.2 OPERATIONAL COMPONENTS APPLICABILITY: Applies to the operating status of the reactor coolant system equipment and related equipment. For the applicable surveillance requirements, see Table 4.1.2.

OBJECTIVE:

To identify those conditions of the reactor coolant system necessary to ensure safe reactor operation.

SPECIFICATIONS: A. At least one pressurizer safety valve shall be operable or open when the reactor head is on the vessel, except for hydrostatic tests.

B. The reactor shall not be made critical or maintained critical unless both pressurizer safety valves are operable.

C. During Modes 1 and 2 and in Mode 3 with reactor trip breakers closed, all three reactor coolant loops and their associated steam generators and reactor coolant pumps shall be in operation. With less than the above required coolant loops in operation, be in at least Hot Standby with reactor trip breakers open within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , except as modified by Specification D below.

D. The limitations of Specification C may be suspended as follows:

1. During Modes 1 and 2, operation may be conducted with 0, 1, 2 or 3 reactor coolant pumps operating at less than 5% of full power for purposes of conducting low power physics testing.

2. During Modes 1 and 2 and in Mode 3 with reactor trip breakers closed, operation may be conducted for less than 24 consecutive hours with one or two reactor coolant pumps operating if reactor power is less than 10% of full power.

E. During Mode 3 with reactor trip breakers open, the following specifications shall apply:

1. At least two of the reactor coolant loops listed below shall be operable:

a. Reactor coolant loop A and its associated steam generator and reactor coolant pump.

b. Reactor coolant loop B and its associated steam generator and reactor coolant pump.

c. Reactor coolant loop C and its associated steam generator and reactor coolant pump.

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2. At least one of the above reactor coolant loops shall be in operation.*

3. With less than the above required reactor coolant loops operable, restore the required loops to operable status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in Hot Shutdown within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4. With no reactor coolant loop in operation, suspend all operations involving a reduction in boron concentration of the reactor coolant system and immediately initiate corrective action to return the required reactor coolant loop to operation.

F. During Mode 4, the following specifications shall apply:

1. At least two of the reactor coolant loops/residual heat removal (RHR) trains listed below shall be operable:

a. Reactor coolant loop A and its associated steam generator and reactor coolant pump.

b. Reactor coolant loop B and its associated steam generator and reactor coolant pump.

c. Reactor coolant loop C and its associated steam generator and reactor coolant pump.

d. Residual heat removal (RHR) pump G-14A and one associated RHR train.

e. Residual heat removal (RHR) pump G-14B and one associated RHR train.

2. At least one of the above loops/trains shall be in operation.**

3. With less than the above required loops/trains operable immediately initiate corrective action to return the required loops/trains to operable status as soon as possible; if the remaining operable loop/train is an RHR train, be in Cold Shutdown within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

All reactor coolant pumps may be de-energized for up to one hour provided (a) no operations are permitted that would cause dilution of the reactor coolant system boron concentration, and (b) core outlet temperature is maintained at least 400F below saturation temperature.

All reactor coolant pumps and residual heat removal pumps may be de-energized for up to one hour provided (a) no operations are permitted that would cause dilution of the reactor coolant system boron concentration, and (b) core outlet temperature is maintained at least 40oF below saturation temperature.

3-7

4. With no loop or train in operation, suspend all operations involving a reduction in boron concentration of the reactor coolant system and immediately initiate corrective action to return one required loop or train to operation.

G. During Mode 5 with reactor coolant loops filled, the following specifications shall apply:

1. At least one residual heat removal (RHR) train shall be operable and in operation,* and either

a. One additional RHR train shall be operable,k" or