ML19253A636
| ML19253A636 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 08/08/1979 |
| From: | Daltroff S PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NUDOCS 7909100605 | |
| Download: ML19253A636 (15) | |
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PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET STREET P.O. BOX 8699 PHILADELPHI A. PA.19101 SHIELDS L. DALTROFF stacra ceno e ion August 8, 1979 Re:
Docket Nos.:
50-277 50-278 IE Bulletin 79-08 Additional Information Mr. Boyce H. Grier, Director Office of Inspection & Enforcement Region I United States Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406
Dear Mr. Grier:
This correspondence is in response to your " Request for Additional Information on IE Bulletin 79-08" as received by telecopy in our office on July 24, 1979.
Responses to your questions are presented below.
Item 2 Question 1 2
1.
Item 2 of IEB 79-08 requires that containment isolation initiation design and procedures be reviewed to assure that manual or automatic isolation is initiated for all lines whose isolation does not degrade needed safety features or cooling capability upon all automatic initiations of safety injection.
This includes those lines designed to transfer potentially radioactive gases and liquids out of containment.
Clarify your response to indicate whether your design and procedures conform to these requirements.
Response
The containment isolation provisions for each fluid system and instrument line which penetrates primary containment have been 331136 7909100 6 6
Mr. Boyce H. Grier Page 2 reviewed.
Attached is a tabulation of these lines and their isolation provisions.
The Peach Bottom design, as other BWR's, does not utilize
" initiation of safety injection" as a signal to initiate isolation of the primary containment.
Automatic isolation valves receive diverse actuation signals from the Primary Containment and Reactor Vessel Isolation Control System (FSAR Section 7.3).
These isolation signals are listed and described on the attached table.
Automatic isolation is initiated for all fluid lines which genetrate the primary containment whose isolation does not degrade needed safety features or cooling capability, with the following exceptions:
a.
Closed Cooling Systems - Closed cooling water lines are provided with one remote manual isolation valve outside containment (see penetrations N-23, 24, 53, 54, 55, 56).
Automatic isolation of these lines is not provided since they provide a heat sink for in containment equipment.
b.
Torus Vacuum Relief Lines - Vacuum in the torus is relieved by two lines between the suppression chamber and the reactor building.
One valve in each line is air operated and is opened when a differential pressure switch de-energizes a de solenoid valve to release air from the air operator.
Thia valve f ails open upon loss of air supply.
The other valve in each line is a self-operating vacuum breaker (see penetrations N-205A, B'.
c.
CRD Hydraulic System - The CRD insert and withdrawal lines are each provided with two isolation barriers.
The first is a ball check valve which is internal to the cont. ol rod drive mechanism.
The outer barrier is provided by valves within each hydraulic control unit (see penetrations N-37, 38).
It has been accepted practice not to provide automatic isolation valves for these lines to preclude a possible failure mechanism of the scram function.
d.
Each TIP System guide tube is provided with an isolation valve which closes automatically upon receipt of a containment isolation signal after the TIP cable and fission chamber have been retracted.
In series with the isolation valve, an additional isolation shear valve is included.
Both valves are located outside the drywell.
In the event of a containment isolation signal, the TIP System receives a command to retract the traveling probes.
Upon full retraction, the isolation valve is closed automatically.
Valve position (full open or full 33113/
Mr. Boyce H. Grier Page 3 closed) of the automatic closing valve is indicated in the main control room.
If a traveling probe does not retract, this information would be supplied to the operator who would investigate the situation to determine if the shear valve should be operated.
This valve is designed to shear the cable and seal the guide tube upon an actuation signal.
Closing of the shear valve is performed by operator action from the main control room.
Each shear valve is operated independently.
The valve is an explosive-type valve, de operated, with monitoring of each actuating circuit provided.
The isolation provisions for all systems designed to transfer potentially radioactive gases and liquids out of containment have also been reviewed.
It has been verified that all of those lines which could transport contaminated fluid to undesirable locations, with the exception of the four sample lines reported previously, have suitable isolation provisions.
Isolation of these lines is provided by normally closed, check, or automatic valves.
The following automatic isolation valves are provided for this purpose.
Each receives an isolation signal upon initiation of its respective system:
MO-13-34, 35 RCIC Stm. Line Drain MO-13-12, 13 RCIC Condensate Pump Dischar6e to Radwaste MO-23-42, 43 HPCI Stm. Line Drain MO-23-39, 40 HPCI Condensate Pump Discharge to Radwaste Item 2 Question 2 1
2.
The isolation procedure for the four conductivity sample lines discussed in your response sheuld be revised to include manual or automatic isolation on all automatic initiations of safety injection.
Provide the results of your engineering design review to determine whether automatic isolation of these lines is required.
Response
Engineering review has indicated that the four conductivity sample lines from the Residual Heat Removal System heat exchangers should be provided with an automatic isolation feature.
A single solenoid valve controlled by the Primary containment Isolacion system is planned for each sample line.
These valves will be seismically and environmentally qualified for this service.
Until these valves can be procured, installed and tested, the isolation procedure discussed in our response to IE Bulletion 79-08 will remain in ef fect.
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Mr. Boyce H. Grier Page 4 Item 2 Question 3 1
3.
Discuss how you intend to provide permanent positive control of the three 3/4-inch lines used for the integrated leak rate test to assure compliance with the requirements of IEB 79-08.
Response
Provisions are being added to lock these valves closed.
As mentioned in our response to IE Bulletin 79-08, a special block (Supervision Safety Block Permit) has been applied to the three 3/4 inch Integrated Leak Rate Test (ILRT) test lines.
Since the only time that these test valves would be used is during a refueling outage for the conduct of the ILRT, a procedural sign-off step is being added to the controlling ILRT procedure to require application of the Safety Block Permit and locking the valve closed for completion of the procedure.
The ILRT procedure must be complete prior to reactor start-up.
These valves will also be on the locked valve list.
Item 2 Question 4 2
4.
Confirm that containment isolation of the Residual Heat Removal Sample Lines is initiated either manually or automatically on all automatic initiations of safety injection.
In addition, provide the results of your engineering design review to determine whether automatic isolation of these lines is required.
Resoonse The four conductivity sample lines from the Residual Heat Removal System heat exchangers as discussed in question 2 above do not presently have automatic isolation on all automatic initiations of the Core Standby Coolant Systems.
This situation will be remedied by adding solenoid valves in each sample line to be controlled by the Primary Containment Isolation System.
Item 2 Question 5 1
5.
Provide a schedule for any actions on item 2 that have not yet been completed.
Resoonse Our present goal is to procure, install and test the Residual Heat Removal System heat exchanger conductivity sample line isolation valves by December 31, 1979.
Until that time, manual isolation will continue to be accomplished as discussed in our response to IE Bulletin 79-08.
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Mr. Boyce H. Grier Page 5 item 7 Question 1 1
Provide the results of your review of the design of systems capable of transferring radioactive gases and liquids out of containment.
Response
1.
The review for the inadvertent release paths has been completed.
No pathways were found which could inadvertently transfer either radioactive liquid or gas out of primary containment.
Those engineered safety features (ESP) systems which are not required to initiate in the event of an accident are isolated and interlocked to prevent inadvertent transfer of radioactive liquids and gases.
Those ESF systems which are required following an accident are not isolated.
Item 7 Question 2 1
2 Verify that inadvertent transfer of radioactive gases or liquids from containment will not occur on resetting engineered safety features instrumentation.
Response
No means were found which could result in an inadvertent transfer of radioactive liquid or gas due to the reaetting of engineered safety features (ESF) instrumentation.
The ESF system designs are such that an action is carried to completion.
Resetting of the isolation requires manual operator action under controlled conditions following instrumentation reset.
Item 7 Question 3 1
3 Discuss the basis upon which continued operability is assured of tne features designed to prevent inadvertent transfer of radioactive gases and liquids out of containment.
Resoonse The functional capability of the Primary Containment Isolation Systems is verified by Technical Specification mandated surveillance tests as follows:
a)
All of the initiating devices are functionally t.:sted every month, b)
Each logic system is functionally tested every 6 months.
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Mr. Boyce H. Grier Page 6 Additionally, administrative procedures assure that these systems are not worked on without specific approval of shift supervision.
Work is performed in accordance with approved work procedures.
Item 8 Question 1 1
1.
We understand from your response that operability tests are performed on redundant safety-related systems prior to removal of any safety-related system from service.
Since you may be relying on prior operability verification within the current Technical Specification surveillance interval, operability should be further verified by at least a visual check of the system to the extent practicable, prior to removing the redundant equipment from service.
Please supplement your response to provide a commitment that you will revise your maintenance and test procedures to adopt this position.
Response
We have revised our " Procedure for Corrective Maintenance" to require that " Shift Supervision shall verify by test or inspection the operability of redundant safety-related (Q-listed) systems required by the Technical Specifications."
The applicable test procedures have been reviewed and revised as necessary to require that any testing that could adversely affect the operability or reliability of a safety-related system is not permitted until verification of any redundant safety-related systems is either done by test or inspection.
Item 8 Question 2 1
2 It is not clear from your response that all involved reactor operational personnel in the oncoming shift are explicitly notified above the status of systems removed from or returned to service.
Please indicate how this information is transferred at shift turnover.
Resoonse Shift Supervision and Operators reporting for duty receive a verbal report from the previous shift covering the following:
a.
General operating condition of the plant.
b.
Specific operations performed and difficulties encountered during the previous shift.
c.
Scheduled plant operations, d.
Equipment outages and maintenance work in progress.
Status of all safety related equipment and conditions.
e.
S M.1 1-
Mr. Boyce H. Grier Page 7 In addition, Shift Supervision and Operatore read past entries in the applicable logs to familiarize themselves with recent plant performance, operations, and problems.
The on-coming man assumes shift responsibility at this point.
Following shift relief, Shift Supervision and Operators make an inspection of instruments, equipment, and areas under their control as early as possible during their shift unless specifically directed otherwise by Shift Supervision or Station Supervision.
During this inspection, priority is given to work areas identified by the previous shift.
This inspection includes a test of Control Room annunciators to verify their operability and a front panel check of ECCS to verify switch, valve and controller status.
In audition, tags are used in the Control Room to indicate the system and equipment status.
These tags are used for mechanical and electrical blocking of equipment and for information regarding equipment status.
The tags do not obscure indicating lights or controls when mounted on the control board.
A meeting is held in the Control Room at the beginning of each shift.
The meeting includes all shift personnel and is lead by the Shift Superintendent and covers applicable topics as follows:
1.
Plant status 2.
Special operations taking place.
3.
Significant maintenance 4
Operating procedure changes 5.
Tech. Spec. chan3es.
6.
Scheduled operations 7.
Shift Superinte, dent's goals for that shift.
Item 10, Question 1 1.
The existing procedures are stated to be under revision.
Please provide your schedule for completion.
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Mr. Boyce H. Grier Page 8
Response
The existing procedures are presently undergoing review and revision with final PORC approval expected prior to August 25, 1979.
Should you have any questions or require additional information, please do not hesitate to contact us.
Very truly yours, 7
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_EO Attachment ec:
United States Nuclear Regulatory Commission Office of Inspection and Enforcement Division of Reactor Operations Inspection Washington, DC 20555 931Eil*
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