ML20133L748

Safety Evaluation Supporting Proposed Recovery Operations Plan Change Request 46

ML20133L748
Person / Time
Site:	Three Mile Island
Issue date:	08/08/1985
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20133L727	List: ML20133L724 ML20133L748
References
NUDOCS 8508120720
Download: ML20133L748 (12)

Text

-

Enclosure 1 SAFETY EVALUATION ,

BY THE OFFICE OF NUCLEAR REACTOR REGULATION FOR REC 0VERY OPERATIONS PLAN CHANGE REQUEST #46 INTRODUCTION By letter dated November 6,1984, the licensee requested the approval of modifications to the Proposed Technical Specifications (PTS) and the RecoveryOperationsPlan(ROP). The staff has concurrently issued a safety evaluation (SE)forthePTSchangesasanattachmenttoanAmendmentof Order which becomes effective September 23, 1985. Discussed herein are R0P changes.

DISCUSSION Section 4.1.1 Boration Control Boron Cooling Water Injection As stated in the staff's discussion on proposed changes to PTS Section 3.1.1 in a concurrently issued Safety Evaluation and Amendment of Order, the Limiting Conditions for Operation related to the operability of the Standby Reactor Coolant System Pressure Control System, the decay heat removal pump and its recirculation pathway, the Mini-Decay Heat Removal System can be deleted. The staff, therefore, concurs with the licensee's proposal to delete the Surveillance Requirements (SR) in the R0P for demonstrating that those systems are operable. Instead, the proposed changes to PTS Section 3.1.1 would require that: (1) two flow paths of the Bordted Water Storage Tank (BWST) downstream of the common dropline be

! operable, (2) the BWST contains at least 390,000 gallons of borated water P Ohoo o PDR

with a boron concentration of between 4,350 and 6,000 ppm, and (3) dedi-I cated on-site equipment for a Reactor Building Sump Recirculation System be operable. -

The licensee has proposed to change the R0P to demonstrate that: (1) the

~ valves associated with the BWST gravity feed pathway are operable, (2) the BWST inventory and boron concentration, as specified in Section 3.1.1, are maintained, and (3) the reactor building sump recirculation pumps are

. operable. These surveillance requirements are appropriate to demonstrate that the PTS Section 3.1.1 requirements are being met. The staff, therefore, concurs with these changes.

Section 4.4.9.1.1 Reactor Coolant System Temperature As stated in the staff's discussions in Section 3.1.1 in a concurrently issued Safety Evaluation and Amendment of Order, decay heat removal is via loss-to-ambient. RCS temperature is affected by decay heat, RCS level and ambient conditions. Licensee's analysis has shown that should the reactor coolant level drain to the bottom of the hot-leg nozzles, an acceptable RCS temperature would still be maintained. Therefore, there is no credible accident that could cause an undesirably high RCS temperature.

Additionally, the licensee is required to maintain reactor building ambient temperature above 50*F. There is no credible event that could cause an undesirably low RCS temperature. The staff, therefore, concurs that the surveillance requirements on RCS temperature can be deleted.

Table 4.3-2 Radiation Monitoring Instrumentation Surveillance Requirements As stated in the staff's discussions in Section 3.1.1 in a concurrently issued Safety Evaluation and Amendment of Order, the staff concurs that the SR for MDHR monitors can be deleted.

- Table 4.3-7 Essential Parameters lionitoring Instrumentation Surveillance Requirements Per discussion in 4.4.9.1.1 above, the RCS temperature channel surveillance requirements are proposed to be deleted. The staff concurs with this proposal.

Section 4.7.3.1 Nuclear Services Closed Cooling System (NSCCS)

Per discussions in Section 3.7.3.1 of the concurrently issued Safety Evaluation and Amendnent of Order, the staff concurs that the SR for the NSCCS can be deleted.

Section 3.7.3.2 Decay Heat Closed Water System (DHCWS)

As discussed in Section 3.7.3.2 of the concurrently issued Safety Evaluation and Amendment of Order, the staff concurs with the proposal to delete the SR for the DHCWS.

Section 4.7.3.3 Mini Decay Heat Removal System (MDHRS)

Per discussion in Section 3.7.3.3 of the concurrently issued Safety Evaluation and Amendment of Order, the staff concurs that the SR for the 11DHRS can be deleted. .

- - ~ --- ~ --m-> .,m , _ _

8 9

e 9

Enclosure 2 O

e N

REC 0VERY OPERATIONS PLAN CHANGES O

o

4 FACILITY GPERATING LICENSE NO. DPR-73 DOCKET NO. 50-320 Replace the follrwing pages of the THI-2 Recovery' Operations Plan with the enclosed pages as indicated.

4.1-1 4.3-4 4.3-5 4.3-11 4.4-1 4.7-1 4.7-2 1

i b

5 l ._ . - . . .

SURVEILLANCE REQUIREMENTS 4.1 WATER INJECTION COOLING AND REACTIVITY CONTROL SYSTEMS 4.1.1 BORATION CONTROL BORATED COOLING WATER INJECTION 4.1.1.1 The systems capable of injecting borated cooling water into the Reactor Coolant System shall be demqnstrated OPERABLE:

A. At least once per 31 days by verifying that each accessible (per occupational exposure considerations) valve in each flowpath that is not locked, sealed, or otherwise secured in position, is in its correct position.

B. At least once per 7 days by:

1. Verifying the boron concentration in the BWST is between 4350 and 6000 ppm.

2. Verifying the contained borated water volume in the BWST is at least 390,000 gallons:

• C. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the BWST temperature is at least 50 degrees Farenheit when the outside temperature is less than 50 degrees Farenheit.

D. At least once per 6 months by verifying the pumps associated with the Reactor Building Sump Recirculation System produce sufficient head and flow to meet makeup requirements.

4.1-1 September 23, 1985 THREE MILE ISLAND - UNIT 2

TABLE 4.3-3 >

RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

, CHANNEL MINIMUM CHANNEL CHANNEL FUNCTIONAL CHANNELS FUNCTIONAL UNIT CHECK CALIBRATION TEST OPERABLE APPLICABILITY ACTION

1. CONTAINMENT

a. Reactor Building Purge Sampler (AMS-3) D SA W 1 Note 1 Note 3 -

2. FUEL HANDLING BUILDING Exhaust Monitors (HPR-221A or H,PR-2218)

a. Gaseous Activity S R M 1 Note S Note 6

b. Particulate Activity S R M 1 Note 5 Note 6

3. SDS MONITORS

a. Process Monitor (IX04) S R H 1 Note 1 Note 4

b. Area Monitor (IX03) S SA M 1 Note 1 Note 2 (See following page for notes)

September 23, 1985

. THREE MILE ISLAND - UNIT 2 a 4.3-4

• e

TABLE 4.3-3 (Con't)

RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS NOTES:

1) During operation of the monitored system.

2) If monitor becomes inoperable, repair or replace by equivalent equipment within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. If not completed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> terminate operation of the monitored system and restore the inoperable monitor (s) to operable status.

3) Restore the inoperable monitor (s) to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

4) If ion exchange effluent monitor is inoperable,' sample on 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> frequency for gross beta. If inoperable longer than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> then terminate operation of ion exchange system and restore the inoperable monitor to operable status.

5) With radioactive waste in the fuel handling building.

6) With the required instrumentation inoperable, suspend all operations involving movement of radioactive wastes in the fuel handling building, restore the inoperable equipment to operable status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

t

. THREE MILE ISLAND - UNIT 2 4.3-5 September 23, 1985

• 4

SURVEILLANCE REQUIREMENTS 4.4 REACTOR COOLANT SYSTEM REACTOR COOLANT LOOPS 4.4.1 Verify that surveillance of the Reactor Coolant System is being performed in accordance with procedures approv.ed pursuant to Specification 6.8.2.

4.4.2 REACTOR VESSEL WATER LEVEL M0NITORING 4.4.2 The Reactor Vessel Level Monitoring Instrumentation shall be demonstrated OPERABLE as required by Table 4.3-7.

SAFETY VALVES  :

4.4.3 Not applicable.

4.4.9 PRESSURE / TEMPERATURE LIMITS REACTOR COOLANT SYSTEM 4.4.9.1.1 Deleted.

4.4.9.1.2 Deleted.

4.4.9.1.3 Deleted.

4.4.9.1.4 The pH of the reactor coolant shall be determined to be greater than or equal to 7.5 and less than 8.4 at least once per 7 days. ,

4.4.9.1.5 The Chloride concentration in the reactor coolant shall be determined to be less than or equal to 5 ppm at least once per 7 days, i

t THREE MILE ISLAND - UNIT 2 4.4-1 September 23, 1985

TABLE 4.3-7 '

ESSENTIAL PARAMETERS MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

• MINIMUM CHANNEL CHANNEL II) READOUT OPERABLE INSTRUMENT CHECK CALIBRATION LOCATION (S) CHANNELS

1. Reactor Building Pressure S R Control Room 2 2.' Reactor Vessel Level S/W(2) SA Control Room (2) 2(2)

3. Incore Thermocouples S R Control Room All Available(3) '.,

or Cable Room

4. NI Intermediate Range M R Cab 217 & 1 Level Log N Control Room

5. NI Source Range Level M R Cab 217(4) & 2 Control Room

6. Reactor Building Water Level NA SA Control Bldg. 1 i

Area West i

7. Borated Water Storage Tank Level S R Control Room 1

8. Steam Generator Level NA NA NA 1/ Generator Notes:

1) Nuclear detectors and all channel components located inside containment may be excluded from CHANNEL CALIBRATION.

2) One channel may consist of a visual indication such as a level standpipe. The seven day surveillance applies to standpipe only. Level standpipe readout may be in the reactor building or by remote television.

3) Report all failures pursuant to Specification 6.9.1.8.

4) Only one readout required at Cab 217.

THREE MILE ISLAND - UNIT 2 ,

4.3-11 September 23, 1985 e

SURVEILLANCE REQUIREMENTS 4.7 PLANT SYSTEMS 4.7.1 FEEDWATER SYSTEM Deleted.

4.7.2 SECONDARY SERVICES CLOSED COOLING WATER' SYSTEM

~

Deleted.

4.7.3 CLOSED CYCLE COOLING WATER SYSTEM NUCLEAR SERVICES CLOSED COOLING SYSTEM 4.7.3.1 Deleted.

THREE MILE ISLAND - UNIT 2 4.7-1 September 23, 1985

SURVEILLANCE REQUIREMENTS DECAY HEAT CLOSED WATER SYSTEM i .

4.7.3.2 ~ Deleted.

MINI DECAY HEAT REMOVAL SYSTEM (M0 HRS) 4.7.3.3 Deleted.

~

f THREE MILE ISLAND - UNIT 2 4.7-2 September 23, 1985

. .