ML19296C535
| ML19296C535 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 02/22/1980 |
| From: | Moody D Maine Yankee |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19296C536 | List: |
| References | |
| RTR-NUREG-0578, RTR-NUREG-578 WMY-80-26, NUDOCS 8002260608 | |
| Download: ML19296C535 (23) | |
Text
.
/
~
f k, AIRE" t
M BARHEE :'
L:
,v,Nme n o,o,,,.,,
e[7 ENGINEEnlNG OF FICE WESTBORo, MASSACHUSETTS 01581 617-36G-9011
....( t B.3.2.1 WMY 80-26 February 22, 1980 United States Nuclear Regulatory Commission Washington, D.C. 20555 Attention:
Office of Nuclear Reactor Regulation Mr. Harold Denton, Director
References:
(a) License No. DPR-36 (Docket No. 50-309)
(b) USNRC Letter to All Operating Nuclear Power Plants, dated October 30, 1979 (c) MYAPC Letter to USNRC dated November 19, 1979 (hM 79-129)
(d) MYAPC Letter to USNRC dated December 17, 1979 (WMY 79-145)
Dear Sir:
Subject:
Implementation Detail of Category A Lessons Learned Your letter, Reference (b), provided additional clarification of NRC staff "Short-Term" requirements, resulting from the TMI investigation, along with corresponding implementation schedules. Our letters, References (c) and (d) provided a detailed commitment to the appropriate actions to address the Category A Lessons Learned items before the plant returned to power operation following its scheduled refueling in January 1980.
Although we committed to address all the Category A items before restart, most of the implementation documentation has been available at the site since early February; however, inspectors from your Eegion I Office of Inspection and Enforcement have not reviewed this material to date.
Instead, a member of your staff has requested that we submit a keyword narrative summary of the actions taken to implement the Category A items. We have developed a summary of those actions undertaken to implement the Category A items, submitted herewith, with the understanding that members of your staff and I&E will visit the plant site to complete the implementation review in the near future.
o 25 8002260 e
U.S. Nuclear Regulatory Commission February 22, 1980 Attention:
Mr. Harold Denton, Director Page 2 The following attachments are provided to enable your staff to initiate the implementation review process:
Attachment A.
A description of what actions were undertaken to implement the respective Category A action items.
Attachment B.
A copy, for continuity, of the eight (8) letters previously submitted, which provided additional implementation review details.
Attachment C.
A description of Category A item 2.2.1.b, Shift Technical Advisor.
Attachment D.
A description of Category A item 2.2.2.b, Onsite Technical Support Center.
We trust you find this information satisfactory; however, please contact us if you have any further questions.
Very truly yours, MAINE YANKEE ATOMIC POWER COMPANY D. E. Moody Manager of Operations EWJ/sec Attachments
ATTACHMENT A 2.1.1 Emergency Power Supply Redundant capability to supply sufficient pressurizer heater, to maintain hot standby natural circulation conditions, from an offsite or emergency power supply presently exists.
Each bank of heaters is connected to an independent power supply via a class IE circuit breaker.
A change is currently being implemented which will provide for stripping of these heaters from the emergency buses upon initiation of a safety injection sigr.al.
Return of the heaters to the emergency bus may be accomplished in the control room.
This enange will be completed prior to plant start up.
(Procedures ha've been established for control of heaters under safety injection or natural circulation conditions.)
The M.O.V. Block valves on the pressurizer relief lines are presently supplied by an emergency power source.
The pressurizer solenoid operated relief valve has been connected to an emergency power supply as discussed in Maine Yankee letter WMY 79-140 dated December 7, 1979.
Pressurizer level instrumentation is presently supplied by an emergency power source.
2.1.2 Safety and Relief Valve Testing Program Endorsement and submission of the EPRI Safety and Relief Valve Testing Program was provided by Maine Yankee letter WMY 79-149 dated December 28, 1979.
The schedule for completion of the test program depends upon the progress of the EPRI program.
2.1 3.A Direct Indication of Salve Position Installation and testing of an acoustic acceleromet.ar system to indicate flow through Maine Yankee safety and relief valves will be completed prior to plant start up.
This system provides indication and alarm in the control room.
Equipment foa this installation meets the requirements of Reference (c) with respect to redundancy, seismic, and environmental qualifications.
2.1 3.B Instrumentation for Inadequate Core Cooling Maine Yankee letter WMY 80-14 dated January 22, 1980 described the existing indicat'.ons used to detsrmine inadequate core cooling.
Procedures to use this information including the margin to saturation provided by the plant computer have been implemented.
In addition, Maine Yankee has purchased and is installing a dedicateu subcooled margin monitor from Combusti.on Engineering.
CE owner's group has evaluated nine concepts for measurint reactor vessel level. These are:
1.
D/P measurement (top of vessel to tne bottom of the hot leg) 2.
Heated Junction Thermocouple 3
Radio Frequency Probe 4.
Floating Source 5.
Fixed Neutron Source and Detector 6.
Floating Dip Stick - Floating Spheres 7.
Ultrasonic Probe 8.
Buoyant Force Transmitter 9
External Standpipe with Float Sensor or D/P Cell.
CE recommends the Heated Junction Thermocouple, however, Maine Yankee is currently reviewing all of the above concepts.
Due to the uncertainties involved with each of these above concepts, a final decision has not been reached on their applicability to Maine Yankee; however, it is anticipated that a resolution will be achieved in time to permit installation by January 1, 1981.
2.1.4 Diverse Containment Isolation The modifications which were described in Maine Yankee letter WMY 79-150 dated December 28, 1979 relative to containment Isolation are nearly completed.
All installation work relative to this required change will be completed prior to plant startup.
2.1.5.A Dedicated H Penetrations 2
As described in Maine Yankee letter WMY 79-151 dated December 28, 1979, Maine Yankee has a dedicated H2 penetration.
2.1.5.C Recombiner Procedures Not applicable.
2.1.6.A Systems Integrity for High Radioactivity Maine Yankee has implemented a leak reduction and preventative maintenance program as described in Maine Yankee letter WMY 80-9 dated January 13, 1980.
2.1.6.B Plant Shielding Review A preliminary review has been conducted to identify all systems carrying post-accident radioactive fluids, assess present shielding, and identify vital access areas which may be affected. Detailed dose calculations are now underway to determine if the NRC dose criteria can be met in performing the necessary operations in these vital areas.
Based upon these dose calculations, alternate procedures will be developed or shielding will be modified to accomodate the emergency functions.
2.1 7.A Automatic Initiation of Auxiliary Feedwater System A Control Grade System for automatic initiation of the auxiliary feedwater system has been designed as described in Maine Yankee letter WMY 80-19 dated February 1, 1980.
Installation is in progress but hookup and activation will not be attempted until NRC review is complete and approval issued as required by NRC letter from R. W.
Reid to R. H. Groce dated December 21, 1979 2.1. 7. B Auxiliary Feedwater Flow Indication Maine Yankee is installing a Control Grade, Controlotron ultrasonic flow sensing system to measure flow to each steam generator with indication on the main control board.
This control grade change will meet the following technical design criteria.
1.
Since Maine Yankee has three steam generators, the auxiliary feedwater flow indication to the steam generators satisfies the single failure criterion.
In addition, each flow channel is backed up by redundant steam generator level indications.
2.
Testability of the auxiliary feedwater flow indication channels shall be a feature of the design. A portable test unit has been purchased for this purpose.
3 Auxiliary feedwater flow instrument channels shall be powered from the vital instrument buses.
2.1.8.A Post-Accident Sampling Maine Yankee letter WMY P9-3 dated January 7, 1980 provided information on the existing sampling capabilities and a description of two concepts for obtaining post-accident samples.
As was indicated in the above referenced letter, in the evaluation of these concepts there are a number of items which require resolution before the final decision is made as to which direction will be pursued. We presently anticipate that the final decision will be made during the month of March which will allow the necessary modifications to be impletri by January 1, 1981.
2.1.8.B High Range Radiation Monitor Procedures for estimating offsite releases using installed battery powered dose measuring equipment have been written and will be implemented prior to startup.
High range radiation monitors to measure containment activity and effluent activity have been selected. Design changes are underway to permit installation by January 1, 1981.
2.1.8.C Improved Iodine Instrumentation As described in Maine Yankee letter WMY 79-129 dated November 19, 1979, Maine Yankee procedures require.the use Of charcoal for iodine sampling and the use of the plant's GeLi detector for gamma ray energy spectrum analysis which can discriminate iodine frem noble gases. The sample collecting equipment is portable.
2.1 9 Transient and Accident Analysis Analysis of small break LOCA and inadequate core cooling has been accomplished by the Combustion Engineering Owner's Group.
Procedure guidelines were developed and reviewed by the NRC.
Emergency procedures have been revised and training provided to all operators.
Other Transient and Accident Analysis required by Reference (b) are being accomplished by the Combustion Engineering Owner's Group according to a scope and schedule agreed to by the Owner's Group and NRC. Results of these analyses are expected by April 1, 1980.
Design development is underway for instrumentation to measure containment pressure, water level, and hydrogen concentration.
Installation will be accomplished by January 1, 1981.
A system for venting the reactor vessel head has been developed as described in Maine Yankee letter WMY 80-8 dated January 10, 1980.
Installation is in progress and it is anticipated that this system will be available prior to plant startup, although not required by NUREG 0578 until January 1981.
2.2.1.A Shift Supervisor Responsibility Maine Yankee has implemented procedures to assure that the duties, responsibilities, and authority of all shift operating personnel are properly defined and that a clear line of authority exists to other plant management personnel.
Thc 3e precedures are being reviewed by the highest level of corporate management and will be promulgated as described in Attachment C prior to plant start up.
2.2.1.B Shift Technical Advisor Maine Yankee has prepared organizational changes to provide the Shift Technical Advisors as required by Reference (b). These changes will be implemented as described in Attachment C.
2.2.1.C Shift and Relief Turnover Procedures Maine Yankee has reviewed and upgraded its Shift and Relief Turnover Procedure as required by Reference (b) for all shift operating perscnnel. This procedure provides a check list to be used by all operators that identifies and provides the status of vital safety parameters and equipment.
2.2.2.A Control Room Access Provisions for controlling access to the control room are included in the procedures described under Item 2.2.1.a above for duties and authority of shift operating personnel.
2.2.2.B Onsite Technical Support Center (TSC)
Maine Yankee has established an onsite Technical Support Center as described in Attachment D.
2.2.2.C Onsite Operational Support Center Maine Yankee has established an onsite Operational Support Center with direct communication to the control room. Procedures for activation and use of this center have been included in the changes to the Emergency Plan requested by Reference (b).
9 9
ATTACIDiENT B
,.px===:
h a
a 1._
MAIRE HARHEE W.'~r !E:":.=: ' "
- TURNPIKE ROAD (RT. 9) e ;CZ.,,1 ENGINEERING OFFICE WESTBORO. MASSACHUSETTS 01581 617-36G-9011
%g g
December 28, 1979 B.3.2 1 WMY 79-149 United States Nuclear Regulatory Commission Washington, D. C.
20555 Attention:
Office of Nuclear Tteactor Regulation Mr. Harold Denton, Director Rcrerences:
(a) License No. DPR-36 (Docket No. 50-309)
(b) NUREG-0578 - Lessons Learned Task Force Status
'rt and Short Term Recommendations dated July, 1979 (c) USNRC Letter to All Operating Nuclear Power Plants dated September 13, 1979 (d) USNRC Letter to All Operating Nuclear Poier Plants dated October 30, 1979
Dear Sir:
Subject:
NUREG-0578, Item 2.1.2, Safety and Relief Valve Testing Program References (c) and (d) in accordance with the recommendation made in reference (a) relative to item 2.1.2 requested that a valve testing program description be submitted for NRC review as part of the Category A Lessons Learned action items.
By letter dated December 17, 1979, Mr. William J. Cahill, Jr., Chairman of the EPRI Safety and Analysis Task Force submitted " Program Plan for the Performance Verification of PWR Safety / Relief Valves and Systems", Revision 2, November 21, 1979 Maine Yankee Atomic Power Company endorses the EPRI program submitted by Mr. Cahill and considers the program to be responsive to the requirements stipulated in NUREG-0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations".
Additionally, Maine Yankee is evaluating alternative programs to accomplish the intent of NUREG item 2.1.2 as clarified by reference (d).
We trust that this information satisfies our commitment relative to submittal of a valve test program; however, should additional questions exist, please contact us.
N q
Very truly yours, d
MAINE YANKEE ATOMIC POWER C0h)ANY
'0 l0 0
V y
Ew ub 9 D. E Moody Manager of Operations EWJ/dmp
- ng a
J MAlliE
- UARHEE nmml01DD'ERCPHIPallU
- ruan,,,e no,o,nr.,,
,7 /
ENGINEERING OFFICE WESTBoRO, MASSACHUS ETTS 01S December 28, 1979 g% JO B.3.2.1 KMY 79-150 United States Nuclear Regulatory Commission Washington, D. C.
20555 Attention:
Office of Nu~ lear Reactor Regulation c
Mr. Harold Denton, Director
References:
(a) License No. DPR-36 (Docket No. 50-309)
(b) NUREG 0578 - Lessons Learned Task Force Status Report and Short Term Recommendations dated July, 1979 (c) USNRC Letter to All Operating Nuclear Power Plants dated September 13, 1979 (d) USNRC Letter to All Operating Nuclear Power Plants dated October 30, 1979 (e) MY Letter to USNRC dated April 26, 1979 (f) MY Letter to USNRC dated May 4,1979
Dear Sir:
Subject:
NUREG-0578, Item 2.1.4 Containment Isolation Reference (d) in addressing recommendations relative to reference (b) item 2.1.4, requested that a determination be made of systems which are considered to be essential and those which are considered to be non-essenital as they relate to a containment isolation system design, and that the results of that determination be submitted to the NRC for review.
References (e) and (f) previously provided information to the NRC in response to I&E Bulletin No.79-06B relative to those systems which could potentially transfer radioactive gasses and liquids outside the containment. An evaluation has been performed of those lines which are isolated on a containment isolation signal to determine whether they can be safely isolated on a safety injection actuation signal. The results of that evaluation and justification for classifying :ertain systems as essential are therefore provided.
The valves have been classified as follows:
N NON-ESSENTIAL 3
V Service DUPLICATE DOCUMENT Component cooling from H.P. drain cooler, pressurizer quench tank Entire document previously cooler, neutron shield tank entered into system under:
ANO No.o[pahes:
IValves which have DC solenoids.