ML20236H841

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Proposed Tech Specs,Increasing Boron Concentration in Standby Liquid Control Sys for Pnpp Cycle 8 Fuel Design & Providing Margin for Future Cycles as Required
ML20236H841
Person / Time
Site: Perry FirstEnergy icon.png
Issue date: 06/30/1998
From:
CENTERIOR ENERGY
To:
Shared Package
ML20236H829 List:
References
NUDOCS 9807070381
Download: ML20236H841 (10)
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Text

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Attachment 3 PY-CEl/NRR-2295L Page 1 of 5 PROPOSED CHANGES TO TECHNICAL SPECIFICATIONS l

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9807070381 980630 PDR ADOCK 05000440 P PDR;

Attachment 3 PY-CEl/NRR-2295L SLC System Page 2 of 5 3.1.7 l

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l . SURVEILLANCE REQUIREMENTS /

SUP,VEILLANCE FREQUENCY (borax- bon'c acid)

SR 3.1.7.1 Verify available volume oftedter_J 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> l THis p nt er:te) solution is within the limits CR of Figure 3.1.7-1. g gg

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borax -boric acid SR 3.1.7.2 Verify temperature of ::dier pent 9er2tc 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> l solution is 2 70*F.

SR 3.1.7.3 Verify temperature of pump suction piping- 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is 2 70*F.

! SR 3.1.7.4 Verify continuity of explosive charge. 31 days SR 3.1.7.5 Verify the concentration of boron in 31 days solution is within the limits of Figure 3.1.7-1. AND l

Once within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after water or boron is added to solution AND Once within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after l solution temperature is restored to 2 70*F (continued)

PERRY - UNIT 1 3.1-21 Amendment No. 69

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Attachment 3 PY-CEl/NRR-2295L SLC System Page 3 of 5 3,1,7 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.1.7.6 Verify each SLC subsystem manual, power 31 days operated, and automatic valve in the flow  !

path that is not locked, sealed, or otherwise secured in position, is in the correct position, or can be aligned to the correct position.

32 4 SR 3.1.7.7- erify each pump develops a flow rate In accordance 2 N lgpm at a discharge pressure with the 7Ml5 2 1220 psig. Inservice CR Testing Program SR 3.1.7.8 Verify flow through one SLC subsystem from 18 months on a pump into reactor pressure vessel. STAGGERED TEST BASIS l

SR 3.1.7.9 Verify all heat traced piping between 18 months-storage tank and pump suction is unblocked. i AND  !

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24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after l pump suction piping l

temperature is i

restored to 2 70*F PERRY - UNIT 1 3.1-22 Amendment No. 69 I

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  • Attachment 3 PY-CEl/NRR-2295L Page 4 of 5 SLC System 3.1.7 R6PQCG WITA h)EvJ FlSURE 3.1.7-j A77AcdED 3

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Figure 3.1. -1 Sodium Penta rate Solution C entration/Volu. Requirements PERRY - UNIT 1 3.1-23 Amendment No. 69

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Attachment 4 PY-CEl/NRR-2295L Page 1 of 5 PROPOSED CHANGES TO TECHNICAL SPECIFICATION BASES "INFORMATION ONLY" l

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, . Attachment 4 PY-CEl/NRR-2295L SLC System Pig] 2 of 5 B 3.1.7 B 3.1 REACTIVITY CONTROL SYSTEMS

'B 3.1.7 Standby Liquid Control (SLC) System BASES BACKGROUND To meet General Design Criterion 26. the SLC System is designed to provide the capability of bringing the reactor.

at any time in a fuel cycle, from full power and minimum control rod inventory (which is at the peak of the xenon transient) to a subcritical condition with the reactor in the most reactive xenon free state without taking credit for control rod movement. In addition, the SLC System satisfies the requirements of 10 CFR 50.62 (Ref.1) on anticipated transient without scram (ATWS).

The SLC System consists of a boron solution storage tank.

two aositive displacement pumps and two explosive valves, whic1 are provided in parallel for redundancy, and associated piping and valves used to transfer borated water from the storage tank to the reactor pressure vessel (RPV).

The borated solution is discharged through~ the high pressure core spray system sparger.

APPLICABLE The SLC System is manually initiated from the control SAFETY ANALYSES room, as directed by the Plant Emergency Instructions, if the operator believes the reactor cannot be shut down, or kept shut down, with the control rods. The SLC System is used in the event that not enough control rods can be inserted to accomplish shutdown and cooldown in the normal TdlS manner. The SLC System injects borated water into the CR reactor core to compensate for all of the various reactivity effects that could occur during plant operation. To meet this objective, it is necessary to inject a que of 8l6 boron that produces a concentration of at leas ppm o natural boron in the reactor core at 68 F. To al ow for potential leakage and imperfect mixing in the reactor system, an additional amount of boron equal to 25% of the amount cited above is added (Ref. 2). The concentration )

i versus volume limits in Figure 3.1.7-1 are calculated such that the required concentration is achieved accounting for l dilution in the RPV with normal water level and including I the water volume in the residual heat removal shutdown i cooling piping and in the recirculation loop piping. This quantity of borated solution is the amount that is above the (continued) i PERRY - UNIT 1 B 3.1-39 Revision Nn. 1 u------------

. . Att:chment 4 PY-CEl/NRR-2295L Paga 3 of 5 SLC System B 3.1.7  !

BASES I ACTIONS eL1 (continued)

OPERABLE subsystem ca)able of performing the intended SLC System function and t1e low probability of a Design Basis Accident (DBA) or transient occurring concurrent with the failure of the Control Rod Drive System to shut down the l reactor. '

B.1  ;

With twa SLC subsystems inoperable. at least one subsystem must be restored to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. The allowed Completion Time of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> is considered acceptable, based on the low probability of a DBA or transient occurring concurrent with t1e failure of the Control Rod Drive System to shut down the reactor.

C.1 If any Required Action and associated Completion Time is not met, the plant must be brought to a MODE in which the LC0 does not ap)1y. T9 achieve this status, the plant must be brought to 10DE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The allowed Completion Time of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is reasonable, based on operating experience, to reach MODE 3 from full power conditions in an orderly manner and without challenging plant systems.

SURVEILLANCE SR 3.1.7.1. SR 3.1.7.2. and SR 3.1.7.3 ~DllSCR REQUIREMENTS 9 SR 3.1.7.1 through SR 3.1.7.3 are 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Surveillance. ,

verifying certain characteristics of the SLC System the volume and temperature of thefeedium cen:rcrx bem- ric "'y' solution in the storage tank, and temperature of the pum) suction piping). thereby ensuring the SLC Sy_ stem OPERABI _ITY without disturbing normal plant operation.fEc tc~ ":cciu ;)

T'WS CM '( pent:bcrate clutien" is uccc 0 describe the rc: alt: fromf These Surveillance 7 mixing ber=) roper ensure the =d beric borated acid solution in water.)

ana temperature.

including tie temperature of the pump suction piping, are maintained. Maintaining a minimum specified borated solution temperature is important in ensuring that the boron remains in solution and does not precipitate out in the  ;

storage tank or in the pum) suction piping. The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> '

Frequency of these SRs is 3ased on operating experience that l has shown there are relatively slow variations in the I measured parameters of volume and temperature. l (continued)

PERRY - UNIT 1 B 3.1-41 Revision No. 1 L-______--_._-_-_----_--____

Attachment 4

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  • PY-CEl/NRR-2295L SLC System Pags4 of 5 B 3.1.7 BASES SURVEILLANCE SR 3.1.7.4 and SR 3.1.7.6 REQUIREtiENTS (continued) SR 3.1.7.4 verifies the continuity of the explosive charges in the injection valves to ensure proper operation will occur if required. Other administrative controls, such as those that limit the shelf life of the explosive charges, must be followed. The 31 day Frequency is based on operating experience that has demonstrated the reliability of the explosive charge continuity.

l SR 3.1.7.6 verifies each valve in the system is in its correct position, but does not apply to the squib (i.e.,

explosive) valves. Verifying the correct alignment for manual, power o)erated, and automatic valves in the SLC System flow pati ensures that the proper flow paths will exist for system operation. A valve is also allowed to be in the nonaccident position, provided it can be aligned to the accident position from the control room, or locally by a dedicated operator at the valve controls. This is acceptable since the SLC System is a manually initiated system. This Surveillance does not apply to valves that are locked, sealed, or otherwise secured in position, since they were verified to be in the correct position prior to locking, sealing, or securing. This verification of valve alignment does not apply to valves that cannot be inadvertently misaligned, such as check valves. This SR does not require any testing or valve manipulation: rather it involves verification that those valves capable of being mispositioned are in the correct positions. The 31 day Frequency is based on engineering judgment and is consistent '

with the procedural controls governing valve operation that ensure correct valve positions.

T415 CE SR 3.1.7.5 borar-boricM. pent:bcr;tc)

This Surveillance solution byrequires an examination using chemicc1 of the :cdt; analysis to ensure Ine pr tank. y ,,,c concentration

cim 3001am ofpcr.;

boron exists

= cr;tc in the storage

cluticr," i; u;cd to 1 descr' bt+he rerults free '""'W
bcrax ar.d beric acid ij THIS CR - -wat+-JSR 3.1.7.5 must be 3erformed anytime boron or water is added to the storage tanc solution to establish that the boron solution concentration is within the specified limits.

This Surveillance must be performed anytime the solution temperature is restored to a: 70 F, to ensure no significant (continued)

PERRY - UNIT 1 B 3.1-42 Revision No. 1

  • Attachment 4 PY-CEl/NRR-2295L 9*

SLC System i B 3.1.7 BASES SURVEILLANCE SR 3.1.7.5 (continued)

REQUIREMENTS boron precipitation occurred. The 31 day Frequency of this Surveillance is appropriate because of the relatively slow variation of boron concentration between surveillance.

TH6 cf. SR 3.1.7.7 l 31.4 rating each SLC System pump develops a flow rate i a gpm at a discharge pressure = 1220 asig ensurbs that pump performance has not degraded during tie fuel cycle.

This minimum pum? flow rate requirement ensures that, when borax-boricacid) combined with EnmcdM cc?2cNtd solution concentration 6_s requirements, the rate of nehative reactivity insertion from the SLC System will adequately compensate for the positive THIS Cg.j reactivity effects encountered during power reduction.

cooldown of the moderator, and xenon decay. This test confirms one point on the pump design curve, and is indicative of overall performance. Such inservice inspections confirm component OPERABILITY. trend performance, and detect incipient failures by indicating abnormal performance. The Frequency of this Surveillance is in accordance with the Inservice Testing Program.

SR 3.1.7.8 and SR 3.1.7.9 1

These Surveillance ensure that there is a functioning flow path from the boron solution storage tank to the RPV, including the firing of an explosive valve. The replacement charge for the ex)losive valve shall be from the same manufactured batc1 as the one fired or from another batch that has been certified by having one of that batch successfully fired. The pump and explosive valve tested should be alternated such that both complete flow paths are tested every 36 months, at alternating 18 month intervals.

The Surveillance may be performed in separate ste)s to prevent injecting boron into the RPV. An accepta)le method for verifying flow from the pump to the RPV is to aump ,

i demineralized water from a test tank through one S_C subsystem and into the RPV. The 18 month Frequency is based  ;

on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance was i performed with the reactor at power. Operating experience (continued)

PERRY - UNIT 1 B 3.1-43 Revision No. 1

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