ML20212A530
| ML20212A530 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 08/31/1997 |
| From: | Ritzman R Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML20211Q653 | List: |
| References | |
| NUDOCS 9710240019 | |
| Download: ML20212A530 (3) | |
Text
.--
+
w.
DOCKET NO.: 50-354 UNIT: Hope Creek DATE: 10/10/97 COMPLETED BY:
R. Ritzman TELEPHONE:
(609) 339-1445
SUMMARY
OF CHANGES, TESTS, AND EXPERIMENTS FOR THE HOPE CREEK GENERATING STATION MONTH SEPTEMBER 1997 The following items completed during August 1997 have been evaluated to determine:
1.
If the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evcluated in the safety analysis report may be increased; or 2.
If a possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report may be created; or 3._-If the margin of safety as defined in the basis for any technical specification is reduced.
The 10CFR50.59 Safety Evaluations showed that these items did not create a new safety hazard to the plant nur did they affect the safe shutdown of the reactor.
These items did not change the plant effluent releases and did not alter the existing environmental impact.
The 10CFR50.59 Safety Evaluations determined that no unreviewed safety or environmental questions are involved.
Desian Chances Summary of Safety Evaluations l
4HE-0104, Pkg.
1, Reconfigure Filtration, Recirculation,
. Ventilation System Low Flow Switch Sensing Tubing.
This design change re-routes the sensing tubing associated with the "C" Filtration, Recirculation, Ventilation System (FRVS) low flow switch, relocates a flow element, and installs drain valves to allow for easier water removal from the system tubing.
The affected instruments are part of FRVS and serve as a barrier to the release of radioactive contamination to the environment by maintaining the Reactor Building at a negative pressure by providing fan start signala.
This design change'will mitigate problems associated with weter accumulation in the flow element sensing lines and correct sloping deficiencies associated with the sensing lines.
9710240019 971015 PDR ADOCK 05000354 R
9 The new configuration will prevent water from accumulating in any zhorizqntal aections, or in any sections that-slope toward the duct.. The' drain valves are-being installed so the water can be drained more easily.
This design change does not negatively impact.any accident response.
This design change does not create or increase the probability or consequences of either an accident or a malfunction of equipment important to safety, or reduce the margin of safety as defined in the basis for any Technical Specification.
Therefore, this design change does not involve an Unreviewed Safety Question.
Temporary Modifications Su==arv of Safety Evaluations There were no changes in this category implemented during August 1997.
UFSAR-Chance Notices Sum==rv cf Safety Evaluations H97-049,-Alternate Residual. Heat Removal - Fuel Pool Cooling and Cleanup Assist Mode.
This UFSAR change notice involves a change to-the facility as described in the SAR, changes to procedures as described in the SAR, and a test not described in the SAk, The alternate Residual Heat Removal - Fuel Pool Cooling and Cleanup (RHR-FPCC) assist mode provides an additional flow path.
Both RHR-FPCC assist modes are used during refueling and are particularly needed during a full core off-load, The alternate mode takes water from the reactor vessel: passes the water through the Residual Heat Remov:~ (RHR) pump, and cools the water
-in the RHR heat exchanger..
Cooling water is then discharged through the drywell spray header and-to the RHR diffusers in the fuel pool.
The alternate mode of RHR-FPCC operation withdraws water at a lower elevation and at a lower temperature than the normal mode.
Both modes meet the design and licensing requirement in that coolant temperature will be maintained so that the coolant _in the fuel pool does not boil during full core
-off-load.
This UFSAR change notice also involves a new decay heat removal method.
This new method uses a reactor recirculation pump for reactor coolant circulation and the alternate RHR-FPCC assist with the Fuel Pool Cooling and Cleanup (FPCC) system.
This back-up method provides a means of satisfying decay heat removal requirements for both the reactor and the fuel pool when the core is.off-loaded and only one RHR train is available.
._..___._. _._ _ _ ~ ___.___ _.- __.
This UFSAR change notice does not_ impact any' accident response.
This VFSAR; change notice does not create or increase the probabilit'y or consequences of either an accident or a malfunction of equipment important to safety, or reduce the margin of safety--as defined in tne basis for any Technical Specification.
Therefore, this UFSAR change notice does not involve an Unreviewed Safety Question.
Procedures Summary of Safety Evaluations HC. OP-AP. ZZ- 0113 (Q), Rev.
1, Emergency Operating Procedure Program Maintenance.
This procedure revision is administrative in nature and changes-the method used to reference current industry practice.
The current industry practice changes include changes to the BWA Owner's Group generic guidance and Emergency Operating Procedure development.
This procedure revision is administrative only and does not impact any accident response.
This procedure revision does not create or increase the probability or consequences of either an accident or a malfunction of equipment important to safety, or reduce the margin of safety as defined in the basis for any Technical Specification.
Therefore, this procedure revision does not involve an Unreviewed Safety Question.
Deficiency Reports Sn==erv of Safety Evaluations There were no changes in this category implemented during August 1997.
Other Summerv of Safety Evaluation There were no-changes in this category implemented during August 1997.
- -