ML20211G289
| ML20211G289 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 10/29/1986 |
| From: | Jaffe D Office of Nuclear Reactor Regulation |
| To: | Opeka J NORTHEAST NUCLEAR ENERGY CO. |
| References | |
| TASK-2.K.3.03, TASK-3.D.3.4, TASK-TM GL-83-36, GL-83-37, TAC-54546, NUDOCS 8611030350 | |
| Download: ML20211G289 (5) | |
Text
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October 29, 1986 Distribution Docket No. 50-336 E'0cchet File-NThompson NRC & L PDRs~ DJaffe PBD-8 Reading PKreutzer FMiraglia ACRS (10)
Mr. John F. Opeka, Senior Vice President OGC-Bethesda Nuclear Engineering and Operations JPartlow Northeast Nuclear Energy Company BGrimes P. O. Box 270 EJordan Hartford, Connecticut 06141-0270 Gray File 3.Sa
Dear Mr. Opeka:
In our continuing effort to identify implementation dates for licensing actions, we noted that the three items described below have been implemented j
in an incomplete manner.
These items are as follows:
TMI Action Item II.K.3.3, " Reporting SV and RV Failures and Challenges" - Our letter of March 8, 1982 expressed the need to formalize the reporting of RV and SV failures and challenges via a change to your Technical Specifications (TS).
No model TS was provided at that time. (TS 6.9.1.5c) herein, provides an acceptable model TS and we request that you propose a similar TS 3
for Millstone 2.
TMI Action Item III.D.3.4, " Control Room Habitability" - On June 19, 1985, the NRC staff issued Amendment No. 100 to Facility Operating License DPR-65 for Millstone Unit 2 which provided TS changes for control room habitability systems.
In the staff's safety evaluation, it was stated that "... the technical specification (change) contains no provisions to periodically verify the licensee's calculational assumptions regarding the control room inleakage during isolation."
We request that you amend your October 14, 1986 submittal concerahg Generic Letter 83-37 (TMI TS) to include a proposed requirement ir the TS for periodic verification of the control room leakage rate.
Secondary Water Chemistry (Multiplant Action - C1) - On July 23, 1979, the NRC sent you a letter requesting that NNECo submit a proposed license condition to require implementation of a secondary 4
I system (steam generator) water chemistry program.
Your letter of September 21, 1979 declined to provide a proposed license condition.
More recently secondary water chemistry program requirements have been established as part of the Administrative (Section 6) TS as shown in Enclosure 2 (Item C).
We request that you reconsider your position on secondary water chemistry TS.
B611030350 861029 PDR ADOCK 05000336 P
. Please respond to the above request for information within 30 days following receipt of this letter.
j This request affects fewer than 10 respondents; therefore OMB clearance is not required.under P.L.96-511.
Sincerely,
/s/
1 D. H. Jaffe, Project Manager PWR Project Directorate #8 Division of PWR Licensing-B f
Enclosures:
As stated i
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4 Mr. John F. Opeka Millstone Nuclear Power Station Northeast Nuclear Energy Company Unit No. 2 cc:
Gerald Garfield, Esq.
Mr. Wayne D. Romberg
- Day, Berry & Howard Superintendent Counselors at Law Millstone Nuclear Power Station City Place P. O. Box 128 Hartford, Connecticut 06103-3499 Waterford, Connecticut 06385 Regional Administrator, Region I Mr. Edward J. Mroczka U.S. Nuclear Regulatory Commission Vice President, Nuclear Operations Office of Executive Director for Northeast Nuclear Energy Company Operations P. O. Box 270 631 Park Avenue Hartford, Connecticut 06141-0270 King of Prussia, Pennsylvania 19406 Mr. Charles Brinkman, Manager Washington Nuclear Operations C-E Power Systems Combustion Engineering, Inc.
7910 Woodmont Avenue Bethesda, Maryland 20814 Mr. Lawrence Bettencourt, First Selectman Town of Waterford Hall of Records - 200 Boston Post Road Waterford, Connecticut 06385 Northeast Utilities Service Compary ATTN:
Mr. Richard R. Laudenat, Manager Generation Facilities Licensing Post Office Box 270 Hartford, Connecticut 06141-0270 Kevin McCarthy, Director Radiation Control Unit De'partment of Environmental Protection State Office Building Hartford, Connecticut 06106 Mr. Theodore Rebelowski U.S. NRC P. O. Box 615 Waterford, Connecticut 06385-0615 Office of Policy & Management ATTN:
Under Secretary Energy Division 80 War ington Street Hartfor1, Connecticut 06106
Reporting of RV and SV Failures and Challenges ADMINISTRATIVE CONTROLS 6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or i
comencement of comercial power operation, or (3) 9 months following initial criticality, whichever is earliest.
If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or comencement of commercial power operation),.supplenentary reports shall be submitted at least every three months until all three events have been completed.
ANNUAL rep 0RTS 1/
6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year. The initial report shall be submitted prior to March 1 of the year following initial criticality.
6.9.1.5 Reports required on an annual basis shall include:
A tabulation on an anaual basis of the number of station, utility, a.
and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their a according to work and job functions gociated man rem exposure.
e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling. The dose assignment to various duty fur.ctions may be estimates based on pocket dosimeter, TLD, or film badge measure-ments. Small exposures totalling less than 20% of the individual total dose need not be accounted for.
In the aggregate, at least i
80% of the total whole body dose received from external sources shall be assigned to specific major work functions.
b.
The complete results of steam generator tube inservice inspections performed during the report period (reference Specification 4.4.5.5.b).
Documentation of all failures and challenges to the pressurizer c.
PORVs or safety valves.
1/ A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station.
2f This tabulation supplements the requirements of $20.407 of 10 CFR Part 20.
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1 Secondary Water Chemistry ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) 1.
Training of personnel, 2.
Procedures for monitoring, and 3.
Provisions for maintenance of sampling and analysis equipment.
c.
Secondary Water Chemistry i
A program for monitoring of secondary water chemistry to inhibit steam generator tube degradation.
This program shall include:
1.
Identification of a sampling schedule for the critical variables and control points for these variables,
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2.
Identification of the procedures used to measure the values of the critical variables, 3.
Identification.of process sampling points, which shall include monitoring the discharge of the condensate pumps for evidence of condenser in-leakage, j
4.
Procedures for the recording and management of data, 5.
Procedures defining corrective actions for all off-control point chemistry conditions, and 6.
A procedure identifying (a) the authority responsible for the interpretation of the data, and (b) the sequence and timing of administrative events required to initiate corrective action.
d.
Post-accident Sampling A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples under accident conditions.
The program shall include the following:
1.
Training of personnel, 2.
Procedures for sampling and analysis, and 3.
Provisions for maintenance of sampling and analysis equipment.
e.
Basemat Monitoring A program for monitoring of the Nuclear Plant Island Structure (NPIS)
Common Foundation Basemat to ensure the continued integrity of the Basemat. The program shall include:
1.
settlement of the basemat 2.
changes in ground water chemistry that could effect corrosion j
of reinforcing steel 3.
seasonal variation in ground water levels
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4.
mapping of significant cracking in the basemat and adjacent walls.
6-16
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