Text

Proposed Changes to Radiological Effluent Tech Spec Pages 3/4 3-63,3/4 3-65 & 3/4 11-13 for Unit 1 & Pages 3/4 3-59, 3/4 3-61 & 3/4 11-13 for Unit 2
	ML17320A465
Person / Time
Site:	Cook
Issue date:	04/14/1983
From:	; INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	;
Shared Package
ML17320A464	List: ML17320A463; ML17320A465;
References
	NUDOCS 8304190444
	Download: ML17320A465 (19)
	v • d • e

ATTACHMENT 1 TO AEP:NRC:0055I LIST OF CHANGES TO APPENDIX A TECHNICAL SPECIFICATIONS DONALD C. COOK NUCLEAR PLANT UNIT 1 <<DPR-58 REMOVE PAGES INSERT PAGES 3/4 3-63 3/4 3-63 3/4 3-65 3/4 3<5 3/4 11-13 3/4 11-13 NOTE: Revisions are noted by a vertical line in the right hand margin of the page.

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ATTACHMENT 2 TO AEP:NRC:0055I LIST OF CHANGES TO APPENDIX A TECHNICAL SPECIFICATIONS DONALD C. COOK NUCLEAR PLANT UNIT 2 - DPR-74 REMOVE PAGES INSERT PAGES 3/4 3-59 3/4 3-59 3/4 3-61 3/4 3%1 3/4 11-13 3/4 11-13 Revisions are noted by a vertical line in the right hand margin of the page .

TABLE 3.3-13 Radicac.ive rase .s "==Hi en- ".Chi =r hc !hs-"...-..eh=a";icn NfhlfiiulA Channe15 Ins rat;ent Oce. ah I e neo I 1 ca51 I i zv Ac ',an Mas e "=as '.-'.41dup ZYs '

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0. C. CQQK - LiHITI 2 Amendment !lo.

~ 4 ~ ~ 0 ATTACHMENT 3 TO AEP:NRC:005 5I . The following are the bases for the proposed Units 1 and 2 Technical Specifications changes and clarifications.

1. Technical Specification 3.11.2.5 states "The concentration of oxygen in the waste gas holdup system shall be limited to < 2% by volume if the hydrogen in the system is > 4% by volume."

Historically, we, have maintained or attempted to maintain the waste gas holdup system at ~ 4% oxygen with hydrogen at > 4%. While operating with these limits, we have experienced several instances where excess oxygen contamination is present. Corrective actions have always been to only reduce the oxygen concentration to c 4%. Typical data over the approx&ate 8-years operation indicates the oxygen concentration in both the gas decay tanks and the CVCS holdup tank gas space is usually 2-3% with approximately 20% of the values between 3-4% oxygen. We have no operating expe'rience with the system at c 2% oxygen in the presence of hydrogen. It is not known whether a concentration of < 2% oxygen can be achieved with our system as it has never occurred or been attempted. Every excursion where the oxygen concentration exceeded 4% can usually be attributed to some finite physical action. The major source of this oxygen contamination has been the introduction of oxygenated water into the CVCS holdup tanks. This had occurred either by recycling an evaporator monitor tank or draining the reactor coolant system or refueling cavity. The recycle of a monitor tank has been administratively addressed and repeat occurrences should not occur. The draining of oxygenated reactor coolant or refueling cavity to the CVCS holdup tanks is being addressed via procedural changes and a design change which should significantly reduce the probability of waste gas, system oxygenation. Once the waste gas system is contaminated with oxygen, a very slow operation of gas purging is undertaken. Initially, any gas decay tanks found to have oxygen contamination at > 4% are sampled for release. The CVCS holdup tank gas space (or spaces) that is (are) contaminated are purged of the oxygen by pumping all available CVCS holdup tank liquid into the contaminated tank. (If more than one CVCS tank gas space is contaminated', the process must be repeated for each tank.) If the tank is not full ( >85% volume) additional liquid must be added. The gas expelled during the filling contaminates another gas decay tank (or more than one) creating a new waste,gas release. Once full, the liquid is then transferred to another CVCS holdup tank and nitrogen is used as 0 ATTACFBKNT 3 AEP:NRC:0055I cover gas during the pumpout. This nitrogen could come from the nitrogen header or a gas decay tank filled with nitrogen. Historically, the oxygen contamination is rarely limited to one CVCS holdup tank gas space, since they are all connected to the ,vent header. An oxygen contamination cycle usually "causes" 4-6 gas decay tank releases. This was with the object to reduce the oxygen to < 4%. If "cleanup" is continued to less than 2% as the Technical Specification required, increase in the nitrogen used will probably increase our gas decay tank releases. In order for ISMECo. to avoid a non-compliance with Technical Specification 3.11.2.5 on April 15, 1983, we request your expedited review and approval of our requested change. We would be glad to provide any further information you need to assist you in your review.

2. Table 3.3-12, Item 3a - There is no "flow monitor" in the turbine building sump effluent line continuous composite sampler as the item implies as written. In Table 4.3-8, the daily channel check of the turbine building sump composite sampler flow monitor (Table 3.3-12, Item 3a) is defined as a visual check of the sample bottle to ensure that a sample is being collected.

3. Table 3.3-13, Item lb requires two oxygen monitors to be operable.

Our current oxygen monitors do not have a high enough reliability level to meet the requirement that both of them be operable at all times. RFC-2591 was written to replace these instruments with a more reliable instrument. The proposed Technical Specification change is required to change Action 29 to allow up to 30-days with only one instrument operable; and Action 30 with no instruments operable if grab samples are taken every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4. Table 3.3-13, Item 3 - The Auxiliary Building Ventilation system is part of the Unit Vent System. Effluent releases via the Auxiliary Building Ventilation System required weekly sample analysis. Action 32 for Table 3.3-13 should specify only weekly analysis requirements of Table 4-11-2 which does not include tritium.

ATTACHMENT 4 TO "AEP: NRC: 0055 Z This Attachment contains a copy of the pages which'require changes in the Appendix A Technical Specifications for Unit 1 (Attachment A) and Unit 2 (Attachment B). These changes were not included in Amendments No. 69 and No. 51. Zt should be noted that these changes were correctly included in the final version of the revised Radiological Effluent Technical Specifications (AEP's letter of September 17, 1982, No. AEP:NRC:0055F) . ATTACHMENT A The following are-the missed changes in the affected pages from Amendment No. 69.

1) Page 1-9 In Table 1.2, the notation for. "P" was not included and should be added.

Amendment No. 51. It was correctly done in Unit 2's

2) Page 6-12 T/S 6.5.2.8 Wrong word It should be "Solidification", not "Modification".

3) Page 6-12 T/S 6.5.2.9,(Definition of Authority of the NSDRC) was missing in its entirety. Again, done in Unit 2's Amendment No. 51, it was correctly

4) Page 6-13 T/S 6.7.1(d), Report submission time of 10 days is inconsistent with Unit 2's time; Submittal time should be 14 days.

- TABLE 1.2 FRE UENCY NOTATION NOTATION ~FRE VENCY At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . At least once per 7 days. At least once per 31 days At least once per 92 days. o SA At least once per 184 days. At least once per S49 days. S/U Prior to each reactor star tup. H.A. Not appl i cab'le. Qo~pl~le.C~J pr or g ~~] re.l g~

0. C. COOK - UNET 1 1-9 Amendment No. 69

DMENI STRATI VE i:QNTRQLS g nl; clil'ica.+i'~~

m. The PROCESS CONTROL PROGRAM and implementing procedures for ti t 'I t p 24 months. i I

n. The performance of activities required by the guality Assurance Pro~ram to meet the criteria of Regulatory Guide 1.21, Rev. 1, 3une 1974 and Regulatory Guide 4.1, Rev. 1, April 1975 at least once per 12 months.

~K'I I Rfc QOQ ('S K j Qlkl g I A 6 )II'ef~ 6.5.2.10 Records of NSDRC activities shall be prepared, approved and distributed as indicated below: a..Minutes of each NSDRC meeting shall be prepared, approved and forwarded to the Vice Chairman, Engineering and Construction, AEPSC, within 14 days following each meeting. R-=.-.r ts of reviews encompassed by Section 6.5.2.7 above, shall be ".re.ared, approved and forwarded to the- Vice Chairman, Engineering . "~ Construction, AEPSC, within 14 days following canpletion of =.".e revi ew. 'udit reports encompassed by Section 6,5.2.8 above, shall be forwarded to the Vice Chairman, Engineering and Construe.ion, <":"SC, and to the management positions responsible for the areas -'i~ted within 30 days a ter completion of the audit.

6. 6 REPQRTABLE OCCURRENCE ACTION 6.6.l 'e following actions shall be taken for REPORTABLE OCCURRENCES:

a. The Conmission shall be notified and/or a report submitted purs>ant to the requirements of Specification 6.9.

b. Each REPORTABLE OCCURRENCE requiring 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months notification to the Canmission shall, be reviewed by the PNSRC and submitted to the HSDRC and the Chief, Nuclear Enoineer.

D. C. COOK - UNIT 1 '-12 Amendment No. 69 ~ 4 P'DMINISTRATIVE ONTROLS 6.7 SAFETY, LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated: .

a. The facility shall be placed in at least HOT STANDBY within one hour.

b. The Safety Limit violation shall be reported to the Commission and to the Chairman of the NSQgC within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

C ~ A Safety Limit Violation Rep~ shall be prepared. The report shall be reviewed by the PNSRC. This report shall describe (1) applicable circumstances preceding the vio1ation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective. action taken to prevent r ecurrence. The Safety Limit Violation Report shall be submitted to the Commission, the Chairman of the NSDRC and the Vice President, Nuclear Engineering within ]ATE days of the violation. 6.8 PROCEDURES o 6.8.1 Mritt n procedure es shall be es.ablished, implemented and main-tained covering the activities refer4ncad below: The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, November, I 1972.

b. Refueling'per'ations.

c. Surveillance and test activities of safety related equipment.

d. Security Plan implementation.=

e. Emergency Plan implementation.

f. Fire Protection Program implem~ntation.

~+ . rsl

g. PROCESS CONTROL PROGRAM implementation.

h. -

OFFSITE DOSE CALCULATION HANUN, implementation.

Rt quality Assurance Program for effluent. and environmental monitoring using the guidance in Regulatory Guide 1.21, Rev. 1, June 1974 and Regulatory Guide 4.1, Rev. 1, April 1975.

6.8.2 Each procedure and administrative policy of 6.8.1 above, and changes .hereto, shall be reviewed bv the PNSRC and approved by the Plant Manager prior to implementation and reviewed periodically as set forth in administrative procedures.

0. C. COOK - UNIT 1 6-13 Amendment No. 69

ATTACHMENT ~ The following are the missed changes in the affected pages from Amendment No. 51.

1) Page XVI a) 6.5.1, Function and Composition indicated as changed to Page 6-6. No new page 6-6 included in submittal and the change indicator should be deleted.

b) 6.5.1, Responsibilities - wrong page 6-7 is listed. It should be 6-6 c) .6.5.1, Authority wrong page 6-8 is listed. It should be 6-7. ~ ~ INDEX ADflL'lISTPATTVE COHTROLS S:-CTEOH PAGE 6 ~ 1 P> o S P Ot s S I rl o L I I Y~ ~ ~ ~ ~ ~ r ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ r ~ ~ ~ ~ ~ ~ ~ 6-1

6. 2 ORGAHl ~T".'ON 0,Tlsl S1 4>> ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ o ~ ~ ~ I ~ 6>>1 F PeC1

'1 i 1 1 leg S iPa7 Cl. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6r3 FAClLITY STA F QUAL>F>CATTOHS..........,..................;, 6-5 6~4 TPv(7H ll)G o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ r o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6-5 6 5 REV~~A AHO AUOli 6.5.1 P~~lT HUC'.~R ~AF~ Y R~~/I~c.< CQ!'2>i ) i-" F QllC i1 On ~ ~ ~ ~ ~ ' ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ o ~ 6>>6 ~ ~ o C ÃIPQS 1 41 On ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ r ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ r ~ ~ r ~ ~ ~ 6>>6 All~o>~~~Os l 4>>o I llo 4>>S ~ ~ ~ ~ ~ ~ ~ ~ r ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ r r ~ r ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6>>loin) I l pile rri ll kl'Qo r r o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~, ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o o ~ lrlerr l~ UOl lllPla ~ ~ ~ ~ ~ ~ r ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ e o ~ o ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ e ~ ~ o ~ O ~ ~ ~ o Raspat;s-chili ~1es...... r m~7 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ o ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ +5>> WU Vl.QZ'1 l.'e'r o ~ o o ~ ~ ~ e ~. ~ ~ ~ o o ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o, r ~ o ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ OlCO i dS ~ ~ ~ o o ~ ~ ~ ~ ~ ~ ~ r ~ o ~ 'e ~ ~ ~ ~ e ~ ~ ~ o ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ e ~ o o o.5.2 HUCL" ~R SAF" Y Ah0 O~miGH RPHPA C"HHE 1 i i-= FUn C>>1 0 t1 ~ ~ ~ ~ o ~ o ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ r' o ~ ~ ~ ~ ~ r ~ ~ o ~ ~ ~ ~ ~ o ~ ~ ~ e ~ ~ o ~ ~ ~ ~ CC,"O OkiivOO ',I 4 I Ofl O o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ o ~ ~ r ~ r i ~ Q>> 5 Al1 lo>>s.. ~ le l sS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ r o ~ ~ ~ ~ ~ ~ ~ ~ ~ 6 a.

0. C. CQCN, - UHiT 2 nYJ Amendment Ho. 51

ML17320A465

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