IR 05000275/1987014
| ML16341E190 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 04/20/1987 |
| From: | Hooker C, Yuhas G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML16341E189 | List: |
| References | |
| 50-275-87-14, 50-323-87-13, NUDOCS 8705050181 | |
| Download: ML16341E190 (18) | |
Text
U.
S.
NUCLEAR REGULATORY, COMMISSION
REGION V
Repor t Nos.
50-275/87-14 and 50-323/87-13 Docket Nos.
50-275 and 50-323 License Nos.
Pacific Gas and Electric Company 77 Beale Street Room 1451 San Francisco, Cali fornia 94106 Facility Name:
Diablo Canyon Units 1 and
Inspection at:
San Luis Obispo County, California Inspection Conducted:
March 30-31 and April 1-3, 1987 Inspector:
C.
A.
o ker, Radi ts n Specialist Approved by:
G.
P.
Yu as, Chief Faci lit s Radiological Protection Section
~Summa r:
Da e Signed D te igned Ins ection on March 30-31 and A ril 1-3 1987 (Re ort Nos.
50-275/87-14 and 50-323/87-13 findings, liquid waste, gaseous waste, preparations for Unit-2 refueling outage, review of licensee reports and facility tours.
Inspection procedures addressed included 30703, 84723, 84724, 83729, 92700, 92701 and 90713.
Results:
Of the areas inspected no violations or deviations were identified.
8705050181 870421 PDR 4DQCK 05000275
DETAILS 1.
Persons Contacted a.
Pacific Gas and Electric Com an PG&E Personnel
- R.
C. Thornberry, Plant Manager
"J.
M. Gisclon, Assistant Plant Manager
"J.
V. Boots, Manager, Chemistry and Radiation Protection (C8RP)
- R.
P.
Powers, Senior C&RP Engineer, Supervisor of Radiation Protection (RP)
"J.
E. Gardner, Senior C&RP Engineer, Supervisor of Chemistry
"G.
L.- Grebel, Supervisor, Regulatory Compliance J.
A. Hays, General Foreman, RP R.
L. Johnson, General Foreman, Chemistry A. 0. Taylor, C&RP Engineer b.
NRC Contacts P.
P.
Narbut, Senior Resident Inspector M.
L. Padovan, Resident Inspector Denotes those present at the exit interview on April 3, 1987.
In addition to the individuals identified above, the inspector met and held discussions with other members of the licensee's staff.
2.
Licensee Action on Previous Ins ection Findin s
I Closed Followu 50-275/87-03-01):
Inspection Report No. 50-275/87-03 documented the inspector's review of a licensee identified violation of TS 6. 12.2 and the need to evaluate the licensee's corrective actions.
Through discussions with licensee representatives and review of new procedural controls, the inspector determined that the licensee's corrective actions were timely and effectively being implemented to prevent recurrence.
The inspector considers this matter closed.
The inspector reviewed the licensee's liquid waste program for compliance with 10 CFR Part 20, TS requirements and recommendations outlined in various industry standards.
a.
Audits The last identified equality Assurance (gA) audit related to this area was discussed in Inspection Report No. 50-275/86-11 and 50-323/86-12.
No violations or deviations were identified.
b.
~Chan es
El
Design Change Notice (DCN) No.
DC2-EJ-34608 for replacement of the existing Post Accident Sampling System (PASS) sampling panel (PM-80)
on Unit 2 was examined.
The replacement of the PM-80 panel will be done during the Unit 2 refueling outage.
The PM-80 panel on Unit 1 was replaced during its refueling outage in 1986.
Repl'acement is being do'ne due to excessive internal and external valve leakage.
The new sample valves are designed for greater pressure integrity for radioactive liquids.
Based on review of this DCN, the inspector
'oted that the licensee concluded that this task could be made in accordance with 10 CFR Part 50.59, since the change did not constitute an unreviewed safety question or require a change to the Technical Specifications.
No violations or deviations were identified.
Effluent Releases The following procedures and documents were reviewed:
Procedures CAP A-5 Li uid Radwaste Dischar e Mana ement CAP A-8 Offsite Dose Calculations Procedure ODCP OPG-1: II Li uid Radwaste S stem - Processin and Dischar e of Documents and Re orts Sel,ected Radioactive Waste Discharge Permits (Form 69-9325)
from January 1, 1987, through April 1, 1987 Semiannual Radioactive Effluent Release Report for the period of July 1, 1986, through December 31, 1986,'iscussed in paragraph 5.a of this report.
Recording Chart 1-49, Radiation Monitoring Liquid Radwaste Process Monitor RE-18 Pulse Cal and Source Checks (attachments to dischar ge permits)
No unmonitored release paths were identified.
Radioactive liquid effluent discharges were observed to be less than the limits specified in 10 CFR Part 20, Appendix B, Table II, Column II.
Sampling and analysis were performed in accordance to TS 4. 11. 1. 1. 1 and radiation doses were calculated using the methodology and parameters in the ODCP to assure compliance with TS 3. 11. 1. 1, 3. 11. 1.2 and 3. 11. 1.3.
Although the licensee was observed to be effectively implementing this program 'to ensure compliance with regulatory requirements, the total quantity of radioactive material released from liquid discharges presented a concern to the inspector and is discussed in paragraph 5. a of this repor In addition to the above observations, the inspector verified by manual calculations the dose values for batch release from Waste Concentrator Condensate Tank No. 02, Permit No. 87-38.
No violations or deviations were identified.
V
~Sam 1 in On March 31, 1987, the inspector observed a
C&RP technician taking a
sample from Spent Regenerate Tank-01 in preparation for a liquid radwaste discharge.
The sample was being drawn from Sample Hood 1-2.
The inspector observed that the technician was dressed and followed procedures in accordance with the radiation work permit, and sampling was conducted in accordance with plant procedures.
During sampling, the inspector observed that air flow indicators (strips of tape)
hanging from the hood window indicated very little air flow through the face of the hood.
The C&RP technician informed the inspector that air flow through this hood has been low for some time.
The technician obtained a air sample from within the hood.
This matter was discussed with a C&RP foreman who informed the inspector that he had submitted an Action Request (AR) several months ago to have the problem corrected.
The inspector obtained a
copy of the AR (No. A0028745)
and noted it had been initiated on July 3, 1986, the problem investigated and a Work Order initiated on July 19, 1986, for maintenance to remove roof partitions to obtain access to the filter bank for further investigation.
It appeared that the problem was associated with air balancing problems that needed further evaluation.
The AR also noted that the low hood flow was a potential radiological problem.
On March 20, 1987, the AR was assigned to the engineering department to correct the problem.
Based oq discussions with the responsible engineer the inspector was informed that the hood air flow problem would be corrected in the near future.
The point that this potential radiological problem had existed for this period without being corrected was discussed at the exit interview on April 3, 1987.
The inspector was informed by the C8RP department that none of the hood-air samples have indicated an airborne problem when taking the liquid radwaste samples from this hood.
No violations or deviations were identified.
Instrumentation The inspector verified that procedures established the method for process and effluent monitor setpoint determination in accordance with the ODCP.
Monitoring instrument calibrations and surveillance tests were discussed with a C&RP engineer and I&C representatives.
Records for the liquid radwaste effluent monitor (RE-18)
and the oily water discharge monitor (RE-03) were examined.
No violations or deviations were identifie e 4.
Gaseous Maste The inspector reviewed the licensee's gaseous program for compliance with
CFR Part 20, TS requirements and recommendations outlined in various industry standards.
a.
Audits The last identified gA audit related to this area was discussed in Inspection Report No. 50-275/86-11 and 50-323/86-12.
No violations or deviations were identified.
b.
Chan<hes There have been no significant changes to the gaseous waste system, other than procedural improvements to enhance the gaseous waste discharge program since the last inspection of this area.
No violations or deviations were identified.
Effluents The following procedures and documents were reviewed:
Procedures CAP A-6 Gaseous Radwaste Dischar e Mana ement CAP A-8 ODCP OP G-2:V Gaseous Radwaste S stem Gas Deca Tank Dischar e
Documents and Re orts Selected Gas Decay Tank Discharge Permits (Form 18-9351)
from January 1,
1987 through April 1, 1987.
Selected Containment Atmosphere Discharge Permits (Form 69-9355)
from January 1,
1987 through April 1, 1987.
Semiannual Radioactive Release Report for the period of July 1, 1986, through December 31, 1986, discussed in paragraph 5. a of this report.
Special Report in accordance with TS 6.9.2 and 3.3.3.6 action d., dated December 15, 1986, discussed in paragraph 5.b of this report Licensee Event Report (LER) No. 86-027-00, discussed in paragraph 5.C of this report.
No unmonitored release paths were identified.
Gaseous effluent discharges were observed to be less than the limits specified in 10
CFR Part 20, Appendix B, Table II, Column I.
Sampling and analysis were performed in accordance to TS 4.11.2.1.2, with the exception of the problem discussed in paragraph 5.c of this report.
Radiation doses were calculated with the methodology and procedures of the
.ODCP to assure compliance with TS 3. 11. 2. 1, 3. 11. 2. 2 and 3. 11. 2. 3.
In addition to the above observations, the inspector verified by manual calculations the site boundary dose values for Gas Decay Tank Discharge No. 87-2-6 and Containment Atmosphere Discharge No.
87-2-67 using the licensee's ODCP.
No violations or deviations were identified.
Instrumentation Records of recent tests of the following selected monitoring systems were examined:
Gaseous Radwaste System Oxygen Monitors (Cells No.
75 and 76),
Units 1 and 2, quarterly calibrations and monthly channel functional tests - TS 4.3.3. 10.
Containment H dro en Monitors Cell No.
Units 1 and 2,
month calibrations - TS 4.6.4.2.
Control Room Chlorine Monitor, Units 1 and 2 monthly channel functional tests
- TS 4.3.3.7.
Plant Vent Flow Rate Monitor FR-12
, Unit 2, 18 month channel calibration - TS 4.3.3.10.
l Plant Vent Noble Gas Monitors RE-14A and 14B, Unit 2, quarterly functional tests - TS 4.3.3.10.
Control Room Air Intake Monitor RM-25, Unit 2, monthly functional tests - TS 4.3.3.1.
In addition to the above reviews, the inspector noted that calibration methods for establishing process monitor set points were described in licensee procedures.
No violations or deviations were identified.
Air Cleanin S stems Records of the following selected recent tests on air cleaning systems were examined:
Control Room Ventilation S stem, monthly tests - TS 4.7.1.b Control Room Ventilation S stem Charcoal Preheater Tests,
month - TS 4.7.5.1. ~
~
Q
~
Auxiliar Buildin Safe uards Air Filtration S stem Test, Unit 2, monthly - TS 4.7.6.1.a and 4. 11.2.4.2 Fuel Handlin Bui ldin Ventilation S stem, Unit 2, monthly - TS 4.9.12.a Fuel Handlin Bui ldin Ventilation Iodine Removal S stem, Unit 1, 18 month - TS 4.9. 12.b, c and d
Based on the above reviews, the inspector determined that the licensee was effectively implementing their TS surveillance program.
No violations or deviations were identified.
5.
Licensee Re orts a ~
Semiannual Radioactive Effluent Release Re ort The licensee's Semiannual Radioactive Release Report for the period of July 1, 1986, through Oecember 31, 1986, was reviewed in-office and during the on-site inspection.
This timely report was issued in accordance with TS 6.9. 1.6 and included a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released
, from both Units as outlined in 'NRC Regulatory Guide 1.21.
This report also included the dose due to the releases of radioactive liquids and gaseous effluents.
Explanations of unplanned gaseous effluent releases were also noted in this report.
Based on this report the following observations were made:
Liquid effluent releases for fission and activation products (not including tritium and gases)
were 2.81 curies for the third quarter and 2.89 curies for the fourth quarter of 1986.
In review of the licensee's January 1, 1986, through June 30, 1986, semiannual effluent report the inspector noted that the licensee had released 4. 7 curies for the first quarter and 0.711 curies the second quarter, a total of ll.11 curies released in 1986.
The national average per plant is about 0.5 curies.
Estimated releases for radioactive liquids in the FSAR are:
Table 11.2-14, for design bases is 0.411 curies/year/Unit (0.822 curies/year total).
Table 11.2-15, for normal operations is 1.6 curies/year/Unit (3. 2 cur ies/year total).
Table 11.2-18, for normal operations with anticipated operational occurrences is 1.75 curies/year/Unit (3.5 curies/year total).
The major contributors to the radioactive liquid releases for 1986 were:
Cobalt-58 (7. 01 curies)
Cobalt-60 (l. 01 curies)
Iron-55 (1.11 curies)
The above isotopes represented about 83K of the activity released.
The licensee has experienced problems in the removal of colloidal contaminants with their liquid radwaste cleanup system.
The licensee was also aware of and were drafting plans for measures to be taken in order to reduce the amount of radioactivity released from liquid discharges.
Review of this report is considered closed (50-275/87-SA-Ol and 50-323/87-SA-01).
However, the effectiveness of the licensee's efforts to reduce radioactivity in liquid discharges will be examined in a subsequent inspection (50-275/87-14-01 and 50-323/87-13-01, Open).
No violations or deviations were identified.
, The licensee's S ecial Re ort on Ino erabilit of Plant Vent Hi h
Ran e Radiation Monitor SR 86-03, dated December 15, 1986, was reviewed in office and discussed with the licensee during the on-site inspection.
This timely report concerning the Unit 2 plant vent high range radiation monitor (RM-29) being inoperable greater than seven days was submitted in accordance with TS 6.9.2 and 3.3.3.6 Action d.
During the inspection the inspector was informed that a replacement monitor was now on-site and will be installed as soon as, machine work can be done on the detector's shield for different cable location.
The inspector verified that the licensee had implemented alternate monitoring methods in accordance with the TS requirements and licensee procedure STP G-16, Alternate Methods of Monitorin for Hi h Ran e Post Accident Radiation Monitor.
No violations or deviations were identified.
c.
LER LER 86-027-00, Missed Surveillance of a Plant Vent Particulate Sam le Due to Personnel Error was reviewed in-office and on-site during the inspection.
The inspector verified that the reporting
~requi rements were met, causes were identified, corrective actions appeared appropriate and had been implemented to prevent recurrence of similar events.
No events or deviations were identified.
6.
Refuelin Outa e Pre arations The inspector discussed licensee preparedness and plans for the Unit 2 refueling outage, scheduled to commence about April 4, 1987, with cognizant CHIRP personnel.
The licensee had contracted for 67 Senior and
k
17 Junior RP technicians to augment the current RP staff.
The licensee was using the same training and qualification requirements for contract RP technicians as used during the Unit 1 refueling outage, which were documented in Inspection Report No. 50-275/86-19.
The inspector also observed that the licensee had installed and was testing six new Eberline PCM-1B personnel contamination monitors.
Four of the monitors were being set up on the 140 ft. elevation for checking containment workers and two were for use at the 85 ft. elevation level access control area.
The licensee had issued a notice regarding use of the PCM-1Bs and instructions for an enhanced survey program to determine the presence of fuel fragments or activated particles.
No violations or deviations were identified.
T The inspector toured various areas of the auxiliary and fuel handling buildings of Unit 1 and Unit 2, and the low-level waste storage facility.
The inspector made independent radiation measurements using a
NRC RO-2 portable ion chamber, S/N 837, due for calibration on May 23, 1987.
During the tours the inspectors observed that all radiation areas and high radiation areas were posted as required by 10 CFR Part 20.
Licensee access and posting controls for high radiation areas were noted to be consistent'with TS, Section 6. 12 and licensee procedures.
Exit Interview The inspector met with the licensee representatives (denoted in paragraph 1) at the coqclusion of the inspection on April 3, 1987.
The scope and findings of the inspection were summarized.
The licensee was informed that no violations or deviations were identified.
With respect to the quantity of radioactive material being released in liquid discharge as described in paragraph 5.a above, the licensee acknowledged the inspector's concer ~
~