ML18142A057
| ML18142A057 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 09/19/1984 |
| From: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML18142A056 | List: |
| References | |
| NUDOCS 8409250323 | |
| Download: ML18142A057 (4) | |
Text
DESCRIPTION
- 1.
Control Rod Assemblies
- 2.
Control Room Assemblies
- 3.
Refueling Water Chemical Addition Tank
- 4.
Pressurizer Safety Valves
- 5.
- 6.
Containment Isolation Trip
- 7.
Refueling System Interlocks
- 8.
Service Water System
- 9.
Fire Protection Pump and Power Supply
- 10.
Primary System Leakage
- 11.
Diesel Fuel Supply
- 12.
Boric Acid Piping Heat Tracing Circuits
- 13.
Main Steam Line Trip TABLE 4.l-2A MINIMUM FREQUENCY FOR EQUlPMENT TESTS TEST Rod drop times of all full length rods at hot conditions Partial movement of all rods Functional Setpoint Setpoint i,Functional i,Functional
"'*Functional Functional
- Evaluate
- Fuel Inventory
- Operational Functional (1) Full closure (2) Partial closure r
FREQUENCY Each refueling shutdown or after disassembly or maintenance requiring the breach of the Reactor Coolant System integrity Every 2 weeks Each refueling shutdown Each refueling shutdown Each refueling shutdown Each refueling shutdown Prior to refueling Each refueling shutdown Monthly Daily 5 days/week Monthly (1) Each cold shutdown (2) Before each startup FSAR SECTION REFERENCE 7*
6 4
10 5
9.12 9.9 9.10 4
8.5 9.1 10 e
t-'l Cl)
~
I-'
I
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ATTACHMENT 2
e-e SAFETY EVALUATION The current requirement for verifying the rod drop time to be no more than 1.8 seconds to dashpot entry for cold conditions, after a refueling shutdown or after maintenance requiring the breach of the Reactor Coolant System integrity (Technical Specifications Table 4.1-2A),
is not necessary. The assumption of a specific rod drop time at cold conditions is not incorporated into any safety analysis.
A comprehensive review of the UFSAR Chapter 14 accident analyses indicates that no transients are assumed to be mitigated by negative reactivity insertion, using control rods, unless the reactor core is at the hot, critical condition. To ensure the availability of the negative reactivity, control rod drop time verification is necessary only before the core attains criticality following reactor heatup. This requirement will be fulfilled by maintaining the Technical Specifications provision for control rod timing tests at hot shutdown.
Therefore, the cold rod drop timing tests will be eliminated without compromising plant safety or any safety analysis.
This change does not adversely affect the safe operation of the plant. This change does not:
- a. -
Increase the probablity of occurrence or the consequences of an accident or malfunction of equipment important to safety, previously evaluated in the safety analysis report.
The assumption of a specific rod drop time at cold conditions is not incorporated into any safety evaluation.
- b.
Create a possibility 'for an accident or malfunction of a different type than any evaluated previously in the safety analysis report.
The verification of conservative rod drop times at hot conditions prior to criticality following a refueling shutdown or after maintenance requiring the breach of the Reactor Coolant System integrity shall continue to be required by the Technical Specifications.
- c.
Reduce the margin to safety as defined in the basis for any Technical Specification.
The assumption of a specific rod drop time at cold conditions is not incorporated into any basis for a Technical Specification.
Therefore, we conclude that this proposed change does not involve a significant hazards consideration or an unreviewed safety question.
J