ML20010J180
| ML20010J180 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 08/13/1981 |
| From: | Leasburg R VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Clark R, Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20010J181 | List: |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, 276, NUDOCS 8109290672 | |
| Download: ML20010J180 (48) | |
Text
{{#Wiki_filter:- \ :: & .p u W rp/ SY Vepco fa )p A 4 b A LN a August 13, 1981 yk e Y Mr. Harold R. Denton, Director Serial No. 276 le.'t$ d . Office of Nuclear Reactor Regulation PSE&C: FCP Mg ATTN: Mr. Robert A. Clark Operating Reactors Branch No. 3 DocketNo.f'0J39>M/w.y/\ License E NPFt7 s Division of Licensing m U.S. Nuclear Reg'.*latory Comission ~Q, ' n:- m E'y v PT b1 ~ Washington, D.C. h]d
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Dear Mr. Denton:
p ige g 3 3r-C": 7 M[f 4 In compliance with 10CFR50.55(e',, NRC Region II was notjfied J .s\ on April 28, 1978 p-ting floor of North Anna Unit 2 could exceed the values presentsthat maximum the FSAR, resulting in the pc,tential for excess exposure to operating personnel. On May 25, 1978, an interim report was submitted to NRC Region II (Serial No. 300) stating that we were investigating several methods of reducing the higher than anticipated radiation levels. In our final report submitted on January 31, 1979, (Serial No. 300A) we described the supplemental shield that had been installed in North Anna Unit 2. Also, in this letter, we stated that we would obtain experime-tal confirmation of the adequacy of the supplemental shield in reducing the Unit 2 containment dose rates. In addressing the effectiveness of the supplemental shielding there are three areas or zones of concern. These zones are defined in Section 12 of the North Anna FSAR and are as follows: Zone I - Continuous access Maximum dose rate: 0.75 mrem /hr Applicable containment location: outside surface of containment including uncontrolled areas of the equipment hatch platform. Zone II - Periodic access Maximum dose rate: 2.5 mrem /hr Applicable containment location: inside reactor containment personnel lock.
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Mr. Harold R. Denton Page 2 Zone IV - Controlled access Maximum dose rate: 100 mrem /hr Applicable containment location: Annulus between crane wall and containment wall. Since the supplemental shielding was installed in Unit 2 prior to startup, there is no pre-shiel' dose rate data available. Therefore, postulated dose rates based on a partial radiation survey conducted in the Unit I containment at 100% power prior to supple-mental shield installation will be used for Unit 2 comparisons. A copy of this survey, conducted on March 14, 1978, is provided as Attachment No. 1. The post-shield dose rate data is from a 100% power survey taken on October 15, 1980. A copy of this survey is provided as Attachment No. 2. The results of the surveys are sumarized below: Maximum dose rate per zone at ' 100% power - mrem /hr Zone Pre-Shield
- Post-Shield I Not available < 0.6 II Not available 3.0 IV 650 50
- Postulated values based on Unit 1 survey. During the Unit 1 survey, certain areas were not surveyed either because they were not included in the planned points or because radiation levels were prohibitive.
The survey values were taken in mrem /hr for neutrons and mR/hr for gammas. The dose rate values for neutrons being in mrem /hr were directly usable. The values for gamas being given as an exposure rate in mR/hr were converted to dose rates in mrem /hr. This conversion was made by assuming a direct one to one relation-chip between R and rem. We feel this is a conservative assumption which is applicable over a broad gama energy spectrum. After conversion, the gama dose rates were added to the neutron values giving total dose rates in mrem /hr. It is these total dose rates , thG are presented above. l i I
Mr. Harold R. Denton Page 3 The comparison of pre-shield and post-shield dose rate values indicates a significant decrease as a result of the installation of the supplemental shielding. In one area, inside the personnel lock, the maximum post-shield dose rate was 3.0 mrem /hr as opposed to the FSAR maximum value of 2.5 mrem /hr. All other areas were within the FSAR limits. We feel this higher value in the personnel lock was caused by an overresponse of the neutron survey instrument. The type of neutron survey instrument used for all surveys was the Eberline Model PNR-4 (nine inch remball). Recent detailed studies conducted by the Environmental Measurement Laboratory of the Department of Energy (EML-376) at North Anna and seven other PWR power stations using bonner sphere neutron spectral analysis indicates the nine inch remball will give dose rate readings from 150 to 185 percent of actual. If it is assumed the neutron dose rates from the survey are 150 percent of actual, the values for the reactor containment personnel lock will drop to within the FSAR limits. We feel this is a conservative assumption and is applicable to this situation. In addition, our letter of March 1,1979, Serial No.123, stated that we would advise you following the completion of the radiation-thermal test if a periodic testing program is warranted for the saddle segments of the supplemental shield. The test results indicate that the shield material will maintain its struc-tural integrity during normal operation in excess of ten years. In the unlikely event that the material begins to deteriorate, it would be detected through radiation surveys made of the containment during entries at power. In addition, the shield material must be removed to complete the periodic inservice inspection of the reactor nozzles. Should material defects be indicated at this time, the defective portion would be replaced at the next outage of sufficient duration. A copy of the radiation-thermal test results is provided as Attachment No. 3 and completes the requirements of condition 2.C.(19) of Amendment No. 2 to License No. NPF-7, dated De ember 29, 1980. l
Mr. Harold R. Denton Page 4 The results of our investigation indicate the adequacy of the supplemental shielding installed in Unit 2 in reducing the maximum containment dose rates to within the FSAR values. Should any significant new information be developed, we ull promptly inform you. Very truly yours, v.:s "Y R. H. Leasburg Vice President - Nuclear Operations FCP/jw Enclosures
Attachment No. 1 Containment Shielding and Radiation Survey North Anna Unit 1 March 14, 1978
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g 25.b i JUN 2'i E73 h, h 5jh 5 f Page 1 of O i -su- s VIRGINIA El.ECTRIC AND POWER COMPANY Revision No.: 1 Date: 12-19-77 12
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STARTUP TEST PROCEDURE FOR NCE"R ANNA POWER STATION UNIT / 1 TITLE: CONTADDENT SHIEDING AND RADIATICN SITRVEY , Preoared 8y: Dennis G. McLain Date: 12-15-7"f Engineering Recommended Acoroval: Date: /)-/f*- 7 7 O . STATION NUCLEAR SAFETY AND OPERATING COMMITTEE APPROVAL OF 'ROCEDURE_: Chairman's Signature: _ Date: /1-/ ?-77
- All personnel conducting actual testing in accordance with this procedure will verify by their signature that they have read i t in its entirety prior to connancing any testing:
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Wyss i AD-9%wn, 6 l?Lw 5/#67xdwisi2i 'W '/: l, . m u L,/ , - 0 TEST RESULTS REVIEVED BY ENGINEERING: [, [. , /_ Date: [-2.l ~78 TEST RESULTS APPROVED BY STATION NUCLEAR SAFETY ANO OPERATING COMMITTEE: Cha irt.ian's Signature: _t Date: b Connents_: [M O' c, f,M ral; M b d ,a h d is ra v) .-.) a k o- i ~a lh - k & 04 LILil w n U (L: T C L fob . '
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SA H.:i RELATTD
TEST RESULTS (Use additlenal pages as needed) py, } ,] DISCREPANC!ES (List by nummer): #% REW LUTION OF 315CREPANCIES (Lis: hv nummer :cersscendine o acove: &w O
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1-SU-8 12-19-77 Page 1 of 5 VIRGINIA IIZCTRIC AND POWER CoffPANY - NORTH ANNA P0hER STATION IJNIT 1 CONTADDENT SHIII. DING AND RADIATION SURVE'T
REFERENCES:
- 1. 7epco Startup Procedure 1-SU-1
- 2. ISAR Table 14.1-2, II.2; III.12
- 3. Power Station Health Physics Radiation Proteccion .v.anual T
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1.0 Purpose 1.1 To asasure the dose rate levels at pre-selected locations inside and outside the contain==nt due to neutron and gamma radiation and to verify the effectiveness of the plant snielding at prior to criticality, hoc zero power, 30"., 50%, 75%, and 100* condi-tions.
1-SU-8 12-19-77 Page 2 of 5 . Initials
.2.0 Initial Conditions
,M 2.1 Iassediately prior to the performance of this test, the Test Engineer has reviewed the latest revisions of the applicable references in order to improve his familiarity.of this procedure of the test. (i.e. Changes to the system, equipment or com-ponent since the procedure was approved will not affect its testing. )
[ 2.2 Verify that all test equipment to be used in the performance of this test is operational and in calibration, and record on the
.) attached IIST EQUI?hENT DATA SHEET.
_ /18/$ 2.3 Notify the Shift Supervisor on duty of the impending test and
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coordinate its performance through him. .
/V/M 2.4 The survey instruments response and better7 condition shall be ~
checked at the beginning and end of the survey. i
/13?/4 2.5 The plant is at the power level prescribed by Reference 1
! ( 9 7 %) and has been in steady state conditions at this power level for at least 2 hours prior to the survey. OJ//4 2.6 Survey teams will consist of a =w- of two personnel,-ad - . WI L .. n . ---- ez u m sm - ' " . , . . = '- - - -- t h O.//4 ' 2.7 Prior to performing the survey, the survey teams have reviewed l the areas and locations to be sureeyed. l OM 2.3 Air samples shm17 be obtained prior to the survey and analyzed for radioactive contamanation levels. f#d, 2.9 A Radiation Work Per: sit has been issued (if applicable). M/p 2.10 The guidelines contained in Reference 3 shall be followed during the survey. -
l 1-SU-8 12-19-77 Page 3 of 5 Initials . 3.0 Precautions Og 3.1 Care shall be exercised at all times during the survey to
=4a4=4 9e dose received by the surveyors. Whenever possible exposure to radiation shall be divided between the members of, each survey team so that dose received by each member will be nearly the same
[jp% 3.2 Prior to entering any area the survey meters will be read while the surveyors are still shielded behind existing barriers. Nh 3.3 The plant should remain a steady state conditions throughout the performance of the survey. If a change in plant power level is required, the survey team must be notified prior to the change. 6 m
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1-50-4 12-19-77 Page 4 of 5
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Initials 4.0 Instructions (MO 4.1 Utilizing Attachment 6.2 take neutron and gamme readings at the
- ~'**4 locationsifjd&!&Wff f" 8dD 4.2 All readings are taken at waist level unless otherwise noted.
General area survey locationa (designated by a C ) will be taken by scanning over 360 degrees and logging the mari = = reading obtained. Contact area locationa (designated by a O)willdetakenatthesinglepointdesignated.
#M 4.3 All readings obtained vill be logged on the enclosed survey maps
.n (Attach = ret 6.2) adjacent to he numbered rymbol described in
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step 4.2 in ar/hr for gamma and in ares /hr for neutron.'
//fM5' 4.4 4t the completion of the survey enter the data obtained on the .
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survey data sheeta.
.. Ar-7 4.5 Recheck the calibration of the survey instruments used and
- record on Attachment 6.1.
3 ##7 4.6 Inform the Shift Supervisor that :he radiation survey at this Power level is complete. i Completed 3y: M# Y0M c/ ri Date: f////78 l l l 1
1-SU-8 12-19-77
, Page 5 of 5
. 5.0 Acceptance Criteria 3.1 Dose rate levels for the power level of conceza have been ob- ,
tained. Any inconsistencies in the obtained data shall be resolved by Health Physics and need not stop further testing unless deemed necessary by the Hesich Physics Supervisor and Operations Supervisor. - 6.0 Attachments 6.1 Test Equipeant and Data Sheet 6.2 Survey Maps A
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1-SU-4 12-19-77 Attachment 6.1
- Page 1 of 1
. TEST EQUIPMENT DATA SHEET i !
i TEST EQUIPMENT DESCRIPTION
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_ W # ffs*?*ft $ d u j* , M/ 4 A/A&& ' y / / // / REviEwEO ev ST ATION NUCLEAR SAFETY AND CPER ATI ECMMITTEE: 13 CN AIRM AN'S SIGN ATU RE: CATE: EceM ENoATieN
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Attachment No. 2 Containment Shielding and Radiation Survey North Anna Unit 2 October 15, 1980 O e l l f i [
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EfCI E #fEORDS 200g b b lb,b JUN O 41981 Page 1 of 2 -SU- 8 1 VIRGINIA ELECTRIC AND POWER COMPANY Revisicn No.: 0 Date: 05-03-79 2 STARTUP TEST PRCCIDURE FOR N AM POWER STATICN UNIT f 2 - TITLE: CCNTAURCl21T SFnnTG mfd MDnMON prev. (Plant Condition) Precared Sv: J. T. SMrnt Date: m.-e_,a Engineering Recemrnended Aceroval: M _ _, f)1 Date: 04-26-79 STATION NUCLEAR SAFETY AND OPERATING COMMITTEE a? PROVAL OF PRCCECURE: Chai .- :an's Signature: \hC
-w^ Oate: 05-03-79 l5
~
All personnel c:ndue:Ing actual testing in ac =rdanca with this procedure will verify 'c y their signature that they have read it in its enti e:y prior to ., cemencing any tes ting: A0 % G la. xQ4e.- bIf'hSil ' )
/$ lN m/ b xe e ldbAbtb$$ l ' #st h ?- A Yv W s 7/
Li TEST RESULTS REVIEWED BY ENGINEEMING: h bg - Date MN/
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75~RESUt.TS AP* ROVED BY STATION WJCLSAR [W/ IN0_0PERATING COMMIME: i i Chai r-an's Signature: p , v
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Cate: [ c - Cements : U , # NOT A CONTROLLED s %. e uMENT
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TEST RESULTS (Use addi:Icnal pages as needed) P [d _ DISCRE?ANCIES (List by number): /[eno /kf( q.9.gf e e RESCLUT1}N OF DISCRE?ANCIES (List by number correscending ec abeve: t</ / [ 47
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2-SU-8 Page 1 of 5 05-03-79 ! I VIRGINIA EI.ECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT 2 CONTAINMENT SHIEI. DING AND RADIATION SURVEY
REFERENCES:
- 1. Vepco Startup Procedure 2-SU-1
- 2. FSAR Table 14.1-2, II.2; III.12
- 3. Health Physics Radiation Protection Manual
- 4. ADMIN-5.0 1.0 Purtose 1.1 To measure the dose rate levels at pre-selected locations inside
, and outside the cocLinment due to neutron and gamuna radiation i
and to verify the effectiveness of the plant shielding at prior to criticality, hot zero power, 30%, 50%, 75%, and 100% condi-tions. i I
, --w-, - - - - --w w,,--, , - , - + -n----w- a
2-SU-3 Page 2 of 5 05-03-79 itials 2.0 Initial Conditions b 2.1 Immediately prior to the performance of this test, the Test Engineer has reviewed the latest revisions of th- applicable references in order to improve his familiarity of this precedure of the test. (i.e. Changes to the system, equipment or com- . ponent since the procedure was approved will not affect its testing.)
.a 2.2 Verify that all test equipment to be used in the performance of this test is operational and in calibration, and record on the attached TEST EQUIPMENT DATA SHEET.
]v 2.3 Notify the Shift Supervisor on duty of the impending test and coordinate its performance through him.
\ 2.4 The survey instruments response and battery condition shall be c$eckedatthebeginningandendofthesurvey.
, (w 2.5 The plant is at the power level prescribed by Reference 1
( TCA ".) and has been in steady state conditions at this power level for at least 2 hcurs prior to the survey. 2.6 Survey teams will consist of a minimum of two personnel, of which one must be a member of the Health Physics Department. \ h~e~- 2.7 Prior to perfo: sing the survey, the survey teams have reviewed the areas and locations to be surveyed. h 2.8 Air sa:nples shall be obtained prior to the survey and analyzed for radioactive contamination levels.
'# 2.9 A Radiation Werk Fermit has been issued (if applicable).
l
. b_ 2.10 The gtr.delines contained in Reference 3 shall be followed during the strvey.
l l l l
2-SU-8 Page 3 of 5 05-03-79 itials 3.0 Precautions 3.1 Care shall be exercised at all times during the survey to mic'aize dose received by the surveyors. Whenever possible exposure to radiation shall be divided between the members of each survey team so that dose received by each member will be nearly the same. 3.2 Prior to enterfe any area the survey meters will be read while the surveyors are still shielded behind existing 3arriers. D" 3.3 The plant should remain a steady state conditions tt oughout the performance of the survey. If a chanue in plant power level is required, the survey team must be notified prior to the change. e
- - ~ - - w- ---u,n - , - n.,. .- -r,- , --mm,- y
6 2-SU-8 Page 4 of 5
- 05-03-79
'nitials 4.0 Instructions N 4.1 Utilizing Attachment 6.2 take neutron and gamma readings at the specified locations.
4.2 General aren survey locations (designated by a O ) will be taken by sc=nning over 360 degrees at waist level and logging the maximum reading obtained. General area survey locations (designated by a b ) will be taken facing the reactor vessel. Contact area locations (designated by a O ) witi be taken st the single point desiy.ated. yW 4.3 All readings obtained will be logged on the enclosed survey maps (Attachment 6.2) adjacent to the numbered symbol described in step 4.2 in cr/hr for gamma and in mrem /hr for neutron.
~.
p 4.4 At the congletion of the surve7 enter the data obtained on the i su'rvey data sheets. b~ D- 4.5 Recheck the calibration of the survey instruments used and record on, Attachment 6.1. 4'. 6 Inform the Shift Supervisor that the radiation survey at this power level is courjlete. Completed By: - Date: TC ~ 6
o . s 2-SU-8 Psge 5 of 5 05-03-79 5.0 Acceptance criteria 5.1 Dose rate levels for the power level of concern have been ob-tained. Any inconsistencies in the obtained data shall be ! i 1 resolved by Health Physics and need not stop further testing , unless deemed necessary by the Supervisor - Health Physics and Operating Supervisor. 6.0 Attachments 6.1 Test Equipment and Data Sheet 6.2 Survey Maps . 6 t l l i e
2-SU-8 Attachment 6.1 Page 1 of 1 05-03-79 TEST EQUIP M DATA SHEET TEST EQUIPMENT DESCRIPTION
- MODEL NUMBER VEPCO QA NLMER
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- NOTE: This applies only to temporarily installed test equipment or instru:nentation Per:nanent instrumentation which is part of the system and shown on' drawings should not be included.
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